Evaluation of the WIPP Project`s compliance with the EPA radiation protection standards for disposal of transuranic waste

DOE Office of Scientific and Technical Information (OSTI.GOV)

Neill, R.H.; Chaturvedi, L.; Rucker, D.F.

The US Environmental Protection Agency`s (EPA) proposed rule to certify that the Waste Isolation Pilot Plant (WIPP) meets compliance with the long-term radiation protection standards for geologic repositories (40CFR191 Subparts B and C), is one of the most significant milestones to date for the WIPP project in particular, and for the nuclear waste issue in general. The Environmental Evaluation Group (EEG) has provided an independent technical oversight for the WIPP project since 1978, and is responsible for many improvements in the location, design, and testing of various aspects of the project, including participation in the development of the EPA standardsmore » since the early 1980s. The EEG reviewed the development of documentation for assessing the WIPP`s compliance by the Sandia National Laboratories following the 1985 promulgation by EPA, and provided many written and verbal comments on various aspects of this effort, culminating in the overall review of the 1992 performance assessment. For the US Department of Energy`s (DOE) compliance certification application (CCA), the EEG provided detailed comments on the draft CCA in March, 1996, and additional comments through unpublished letters in 1997 (included as Appendices 8.1 and 8.2 in this report). Since the October 30, 1997, publication of the EPA`s proposed rule to certify WIPP, the EEG gave presentations on important issues to the EPA on December 10, 1997, and sent a December 31, 1997 letter with attachments to clarify those issues (Appendix 8.3). The EEG has raised a number of questions that may have an impact on compliance. In spite of the best efforts by the EEG, the EPA reaction to reviews and suggestions has been slow and apparently driven by legal considerations. This report discusses in detail the questions that have been raised about containment requirements. Also discussed are assurance requirements, groundwater protection, individual protection, and an evaluation of EPA`s responses to EEG`s comments.« less

Development of Modern Performance Assessment Tools and Capabilities for Underground Disposal of Transuranic Waste at WIPP

NASA Astrophysics Data System (ADS)

Zeitler, T.; Kirchner, T. B.; Hammond, G. E.; Park, H.

2014-12-01

The Waste Isolation Pilot Plant (WIPP) has been developed by the U.S. Department of Energy (DOE) for the geologic (deep underground) disposal of transuranic (TRU) waste. Containment of TRU waste at the WIPP is regulated by the U.S. Environmental Protection Agency (EPA). The DOE demonstrates compliance with the containment requirements by means of performance assessment (PA) calculations. WIPP PA calculations estimate the probability and consequence of potential radionuclide releases from the repository to the accessible environment for a regulatory period of 10,000 years after facility closure. The long-term performance of the repository is assessed using a suite of sophisticated computational codes. In a broad modernization effort, the DOE has overseen the transfer of these codes to modern hardware and software platforms. Additionally, there is a current effort to establish new performance assessment capabilities through the further development of the PFLOTRAN software, a state-of-the-art massively parallel subsurface flow and reactive transport code. Improvements to the current computational environment will result in greater detail in the final models due to the parallelization afforded by the modern code. Parallelization will allow for relatively faster calculations, as well as a move from a two-dimensional calculation grid to a three-dimensional grid. The result of the modernization effort will be a state-of-the-art subsurface flow and transport capability that will serve WIPP PA into the future. Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. This research is funded by WIPP programs administered by the Office of Environmental Management (EM) of the U.S Department of Energy.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Young, J.; Ajo, H.; Brown, L.

Analysis of the recent WIPP samples are summarized in this report; WIPP Cam Filters 4, 6, 9 (3, 7, 11 were analyzed with FAS-118 in a separate campaign); WIPP Drum Lip R16 C4; WIPP Standard Waste Box R15 C5; WIPP MgO R16 C2; WIPP MgO R16 C4; WIPP MgO R16 C6; LANL swipes of parent drum; LANL parent drum debris; LANL parent drum; IAEA Swipe; Unused “undeployed” Swheat; Unused “undeployed” MgO; and Masselin cloth “smears”. Analysis showed that the MgO samples were very pure with low carbonate and water content. Other samples showed the expected dominant presence of Mg, Namore » and Pb. Parent drum debris sample was mildly acidic. Interpretation of results is not provided in this document, but rather to present and preserve the analytical work that was performed. The WIPP Technical Analysis Team is responsible for result interpretation which will be written separately.« less

Technical basis for external dosimetry at the Waste Isolation Pilot Plant (WIPP)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Bradley, E.W.; Wu, C.F.; Goff, T.E.

1993-12-31

The WIPP External Dosimetry Program, administered by Westinghouse Electric Corporation, Waste Isolation Division, for the US Department of Energy (DOE), provides external dosimetry support services for operations at the Waste Isolation Pilot Plant (WIPP) Site. These operations include the receipt, experimentation with, storage, and disposal of transuranic (TRU) wastes. This document describes the technical basis for the WIPP External Radiation Dosimetry Program. The purposes of this document are to: (1) provide assurance that the WIPP External Radiation Dosimetry Program is in compliance with all regulatory requirements, (2) provide assurance that the WIPP External Radiation Dosimetry Program is derived from amore » sound technical base, (3) serve as a technical reference for radiation protection personnel, and (4) aid in identifying and planning for future needs. The external radiation exposure fields are those that are documented in the WIPP Final Safety Analysis Report.« less

Vertical Flume Testing of WIPP Surrogate Waste Materials

NASA Astrophysics Data System (ADS)

Herrick, C. G.; Schuhen, M.; Kicker, D.

2012-12-01

The Waste Isolation Pilot Plant (WIPP) is a U.S. Department of Energy geological repository for the permanent disposal of defense-related transuranic (TRU) waste. The waste is emplaced in rooms excavated in the bedded Salado salt formation at a depth of 655 m below ground surface. After emplacement of the waste, the repository will be sealed and decommissioned. The DOE demonstrates compliance with 40 CFR 194 by means of performance assessment (PA) calculations conducted by Sandia National Laboratories. WIPP PA calculations estimate the probability and consequences of radionuclide releases for a 10,000 year regulatory period. Human intrusion scenarios include cases in which a future borehole is drilled through the repository. Drilling mud flowing up the borehole will apply a hydrodynamic shear stress to the borehole wall which could result in erosion of the waste and radionuclides being carried up the borehole. WIPP PA uses the parameter TAUFAIL to represent the shear strength of the degraded waste. The hydrodynamic shear strength can only be measured experimentally by flume testing. Flume testing is typically performed horizontally, mimicking stream or ocean currents. However, in a WIPP intrusion event, the drill bit would penetrate the degraded waste and drilling mud would flow up the borehole in a predominantly vertical direction. In order to simulate this, a flume was designed and built so that the eroding fluid enters an enclosed vertical channel from the bottom and flows up past a specimen of surrogate waste material. The sample is pushed into the current by a piston attached to a step motor. A qualified data acquisition system controls and monitors the fluid's flow rate, temperature, pressure, and conductivity and the step motor's operation. The surrogate materials used correspond to a conservative estimate of degraded TRU waste at the end of the regulatory period. The recipes were previously developed by SNL based on anticipated future states of the waste considering inventory, changes in the underground environment, and theoretical and experimental results. The recipes represent the degraded waste in its weakest condition; simulating 50, 75, and 100% degradation by weight. The percent degradation indicates the anticipated amount of iron corrosion and decomposition of cellulosics, plastics, and rubbers. Samples were die compacted to two pressures, 2.3 and 5.0 MPa. Testing has established that the less degraded the surrogate material is and the higher the compaction stress it undergoes, the stronger the sample is. The 50% degraded surrogate waste material was accepted for use in obtaining input parameters for another WIPP PA model by a conceptual model peer review panel and the EPA. The use of a 50% degraded surrogate waste in vertical flume testing would provide an improved estimate of the waste shear strength and establish consistency between PA models in the approach used to obtain input parameters. Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. This research is funded by WIPP programs administered by the Office of Environmental Management (EM) of the U.S Department of Energy.

Vertical Flume Testing of WIPP Surrogate Waste Materials

NASA Astrophysics Data System (ADS)

Herrick, C. G.; Schuhen, M.; Kicker, D.

2013-12-01

The Waste Isolation Pilot Plant (WIPP) is a U.S. Department of Energy geological repository for the permanent disposal of defense-related transuranic (TRU) waste. The waste is emplaced in rooms excavated in the bedded Salado salt formation at a depth of 655 m below ground surface. After emplacement of the waste, the repository will be sealed and decommissioned. The DOE demonstrates compliance with 40 CFR 194 by means of performance assessment (PA) calculations conducted by Sandia National Laboratories. WIPP PA calculations estimate the probability and consequences of radionuclide releases for a 10,000 year regulatory period. Human intrusion scenarios include cases in which a future borehole is drilled through the repository. Drilling mud flowing up the borehole will apply a hydrodynamic shear stress to the borehole wall which could result in erosion of the waste and radionuclides being carried up the borehole. WIPP PA uses the parameter TAUFAIL to represent the shear strength of the degraded waste. The hydrodynamic shear strength can only be measured experimentally by flume testing. Flume testing is typically performed horizontally, mimicking stream or ocean currents. However, in a WIPP intrusion event, the drill bit would penetrate the degraded waste and drilling mud would flow up the borehole in a predominantly vertical direction. In order to simulate this, a flume was designed and built so that the eroding fluid enters an enclosed vertical channel from the bottom and flows up past a specimen of surrogate waste material. The sample is pushed into the current by a piston attached to a step motor. A qualified data acquisition system controls and monitors the fluid's flow rate, temperature, pressure, and conductivity and the step motor's operation. The surrogate materials used correspond to a conservative estimate of degraded TRU waste at the end of the regulatory period. The recipes were previously developed by SNL based on anticipated future states of the waste considering inventory, changes in the underground environment, and theoretical and experimental results. The recipes represent the degraded waste in its weakest condition; simulating 50, 75, and 100% degradation by weight. The percent degradation indicates the anticipated amount of iron corrosion and decomposition of cellulosics, plastics, and rubbers. Samples were die compacted to two pressures, 2.3 and 5.0 MPa. Testing has established that the less degraded the surrogate material is and the higher the compaction stress it undergoes, the stronger the sample is. The 50% degraded surrogate waste material was accepted for use in obtaining input parameters for another WIPP PA model by a conceptual model peer review panel and the EPA. The use of a 50% degraded surrogate waste in vertical flume testing would provide an improved estimate of the waste shear strength and establish consistency between PA models in the approach used to obtain input parameters. Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. This research is funded by WIPP programs administered by the Office of Environmental Management (EM) of the U.S Department of Energy.

Historical Background on Assessment the Performance of the Waste Isolation Pilot Plant

DOE Office of Scientific and Technical Information (OSTI.GOV)

Rechard, R.P.

1999-06-01

In 1979, six years after selecting the Delaware Basin as a potential disposal area, Congress authorized the US Department of Energy to build the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, as a research and development facility for the safe management, storage, and disposal of waste contaminated with transuranic radioisotopes. In 1998, 19 years after authorization and 25 years after site selection, the US Environmental Protection Agency (EPA) certified that the WIPP disposal system complied with its regulations. The EPA's decision was primarily based on the results from a performance assessment conducted in 1996. This performance assessment wasmore » the culmination of four preliminary performance assessments conducted between 1989 and 1992. This report provides a historical setting and context for how the performance of the deep geologic repository at the WIPP was analyzed. Also included is background on political forces acting on the project. For example, the federal requirement to provide environmental impact statements and negotiated agreements with the State of New Mexico influenced the type of scientific areas that were investigated and the engineering analysis prior to 1989 for the WIPP.« less

Waste Isolation Pilot Plant (WIPP) conceptual design report. Part I: executive summary. Part II: facilities and system

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1977-06-01

The pilot plant is developed for ERDA low-level contact-handled transuranic waste, ERDA remote-handled intermediate-level transuranic waste, and for high-level waste experiments. All wastes placed in the WIPP arrive at the site processed and packaged; no waste processing is done at the WIPP. All wastes placed into the WIPP are retrievable. The proposed site for WIPP lies 26 miles east of Carlsbad, New Mexico. This document includes the executive summary and a detailed description of the facilities and systems. (DLC)

Information brochure on the Department of Energy's proposed Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. Project overview

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

This project overview comprises the following: project history; WIPP fact sheet; legal actions required; major WIPP milestones; low-level waste volumes; nuclear waste transportation; WIPP site selection; and questions and answers from the Department of Energy request for public input prior to public meetings in Roswell and Hobbs, New Mexico.

Regulatory basis for the Waste Isolation Pilot Plant performance assessment

DOE Office of Scientific and Technical Information (OSTI.GOV)

HOWARD,BRYAN A.; CRAWFORD,M.B.; GALSON,D.A.

2000-05-22

The Waste Isolation Pilot Plant (WIPP) is the first operational repository designed for the safe disposal of transuranic (TRU) radioactive waste from the defense programs of the US Department of Energy (DOE). The US Environmental Protection Agency (EPA) is responsible for certifications and regulation of the WIPP facility for the radioactive components of the waste. The EPA has promulgated general radioactive waste disposal standards at 40 CFR Part 191. and WIPP-specific criteria to implement and interpret the generic disposal standards at 40 CFR Part 194. In October 1996. the DOE submitted its Compliance Certification Application (CCA) to the EPA tomore » demonstrate compliance with the disposal standards at Subparts B and C of 40 CFR Part 191. This paper summarizes the development of the overall legal framework for radioactive waste disposal at the WIPP, the parallel development of the WIPP performance assessment (PA), and how the EPA disposal standards and implementing criteria formed the basis for the CCA WIPP PA. The CCA resulted in a certification in May 1998 by the EPA of the WIPP'S compliance with the EPA's disposal standard, thus enabling the WIPP to begin radioactive waste disposal.« less

Development and application of an analysis methodology for interpreting ambiguous historical pressure data in the WIPP gas-generation experiments.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Felicione, F. S.

2006-01-23

The potential for generation of gases in transuranic (TRU) waste by microbial activity, chemical interactions, corrosion, and radiolysis was addressed in the Argonne National Laboratory-West (ANL-West) Gas-Generation Experiments (GGE). Data was collected over several years by simulating the conditions in the Waste Isolation Pilot Plant (WIPP) after the eventual intrusion of brine into the repository. Fourteen test containers with various actual TRU waste immersed in representative brine were inoculated with WIPP-relevant microbes, pressurized with inert gases, and kept in an inert-atmosphere environment for several years to provide estimates of the gas-generation rates that will be used in computer models formore » future WIPP Performance Assessments. Modest temperature variations occurred during the long-term ANL-West experiments. Although the experiment temperatures always remained well within the experiment specifications, the small temperature variation was observed to affect the test container pressure far more than had been anticipated. In fact, the pressure variations were so large, and seemingly erratic, that it was impossible to discern whether the data was even valid and whether the long-term pressure trend was increasing, decreasing, or constant. The result was that no useful estimates of gas-generation rates could be deduced from the pressure data. Several initial attempts were made to quantify the pressure fluctuations by relating these to the measured temperature variation, but none was successful. The work reported here carefully analyzed the pressure measurements to determine if these were valid or erroneous data. It was found that a thorough consideration of the physical phenomena that were occurring can, in conjunction with suitable gas laws, account quite accurately for the pressure changes that were observed. Failure of the earlier attempts to validate the data was traced to the omission of several phenomena, the most important being the variation in the headspace volume caused by thermal expansion and contraction within the brine and waste. A further effort was directed at recovering useful results from the voluminous archived pressure data. An analytic methodology to do this was developed. This methodology was applied to each archived pressure measurement to nullify temperature and other effects to yield an adjusted pressure, from which gas-generation rates could be calculated. A review of the adjusted-pressure data indicated that generated-gas concentrations among these containers after approximately 3.25 years of test operation ranged from zero to over 17,000 ppm by volume. Four test containers experienced significant gas generation. All test containers that showed evidence of significant gas generation contained carbon-steel in the waste, indicating that corrosion was the predominant source of gas generation.« less

Using 3D Geologic Models to Synthesize Large and Disparate Datasets for Site Characterization and Verification Purposes

NASA Astrophysics Data System (ADS)

Hillesheim, M. B.; Rautman, C. A.; Johnson, P. B.; Powers, D. W.

2008-12-01

As we are all aware, increases in computing power and efficiency have allowed for the development of many modeling codes capable of processing large and sometimes disparate datasets (e.g., geological, hydrological, geochemical, etc). Because people sometimes have difficulty visualizing in three dimensions (3D) or understanding how multiple figures of various geologic features relate as a whole, 3D geologic models can be excellent tools to illustrate key concepts and findings, especially to lay persons, such as stakeholders, customers, and other concerned parties. In this presentation, we will show examples of 3D geologic modeling efforts using data collected during site characterization and verification work at the Waste Isolation Pilot Plant (WIPP). The WIPP is a U.S. Department of Energy (DOE) facility located in southeastern New Mexico, designed for the safe disposal of transuranic wastes resulting from U.S. defense programs. The 3D geologic modeling efforts focused on refining our understanding of the WIPP site by integrating a variety of geologic data. Examples include: overlaying isopach surfaces of unit thickness and overburden thickness, a map of geologic facies changes, and a transmissivity field onto a 3D structural map of a geologic unit of interest. In addition, we also present a 4D hydrogeologic model of the effects of a large-scale pumping test on water levels. All these efforts have provided additional insights into the controls on transmissivity and flow in the WIPP vicinity. Ultimately, by combining these various types of data we have increased our understanding of the WIPP site's hydrogeologic system, which is a key aspect of continued certification. Sandia is a multi program laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy's National Nuclear Security Administration under Contract DE-AC04- 94AL85000. This research is funded by WIPP programs administered by the Office of Environmental Management (EM) of the U.S Department of Energy.

WIPP Magnesium Oxide (MgO) - Planned Change Request

EPA Pesticide Factsheets

On April 10, 2006, the DOE submitted a planned change request pertaining to the amount of MgO emplaced in the WIPP repository. MgO is an engineered barrier that DOE included as part of the original WIPP Certification Decision.

Project Plan: Salt in Situ Heater Test.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kuhlman, Kristopher L.; Mills, Melissa Marie; Herrick, Courtney G.

This project plan gives a high-level description of the US Department of Energy Office of Nuclear Energy (DOE-NE) Spent Fuel and Waste Disposition (SFWD) campaign in situ borehole heater test project being planned for the Waste Isolation Pilot Plant (WIPP) site This plan provides an overview of the schedule and responsibilities of the parties involved. This project is a collaborative effort by Sandia, Los Alamos, and Lawrence Berkeley National Laboratories to execute a series of small-diameter borehole heater tests in salt for the DOE-NE SFWD campaign. Design of a heater test in salt at WIPP has evolved over several years.more » The current design was completed in fiscal year 2017 (FY17), an equipment shakedown experiment is underway in April FY18, and the test implementation will begin in summer of FY18. The project comprises a suite of modular tests, which consist of a group of nearby boreholes in the wall of drifts at WIPP. Each test is centered around a packer-isolated heated borehole (5" diameter) containing equipment for water-vapor collection and brine sampling, surrounded by smaller-diameter (2" diameter) satellite observation boreholes. Observation boreholes will contain temperature sensors, tracer release points, electrical resistivity tomography (ERT) sensors, fiber optic sensing, and acoustic emission (AE) measurements, and sonic velocity sources and sensors. These satellite boreholes will also be used for plugging/sealing tests. The first two tests to be implemented will have the packer-isolated borehole heated to 120°C, with one observation borehole used to monitor changes. Follow-on tests will be designed using information gathered from the first two tests, will be conducted at other temperatures, will use multiple observation boreholes, and may include other measurement types and test designs.« less

Background Underground at WIPP

NASA Astrophysics Data System (ADS)

Esch, Ernst-Ingo; Hime, A.; Bowles, T. J.

2001-04-01

Recent interest to establish a dedicated underground laboratory in the United States prompted an experimental program at to quantify the enviromental backgrounds underground at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. An outline of this program is provided along with recent experimental data on the cosmic ray muon flux at the 650 meter level of WIPP. The implications of the cosmic ray muon and fast neutron background at WIPP will be discussed in the context of new generation, low background experiments envisioned in the future.

L-3 Com AVISYS civil aviation self-protection system

NASA Astrophysics Data System (ADS)

Carey, Jim

2006-05-01

In early 2004, L-3 Com AVISYS Corporation (hereinafter referred to as L-3 AVISYS or AVISYS) completed a contract for the integration and deployment of an advanced Infrared Countermeasures self-protection suite for a Head of State Airbus A340 aircraft. This initial L-3 AVISYS IRCM Suite was named WIPPS (Widebody Integrated Platform Protection System). The A340 WIPPS installation provisions were FAA certified with the initial deployment of the modified aircraft. WIPPS is unique in that it utilizes a dual integrated missile warning subsystem to produce a robust, multi-spectral, ultra-low false alarm rate threat warning capability. WIPPS utilizes the Thales MWS-20 Pulsed Doppler Radar Active MWS and the EADS AN/AAR-60 Ultraviolet Passive MWS. These MWS subsystems are integrated through an L-3 AVISYS Electronic Warfare Control Set (EWCS). The EWCS also integrates the WIPPS MWS threat warning information with the A340 flight computer data to optimize ALE-47 Countermeasure Dispensing System IR decoy dispensing commands, program selection and timing. WIPPS utilizes standard and advanced IR Decoys produced by ARMTEC Defense and Alloy Surfaces. WIPPS demonstrated that when IR decoy dispensing is controlled by threat range and time-to-go information provided by an Active MWS, unsurpassed self protection levels are achievable. Recognizing the need for high volume civil aviation protection, L-3 AVISYS configured a variant of WIPPS optimized for commercial airline reliability requirements, safety requirements, supportability and most importantly, affordability. L-3 AVISYS refers to this IRCM suite as CAPS (Commercial Airliner Protection System). CAPS has been configured for applications to all civil aircraft ranging from the small Regional Jets to the largest Wide-bodies. This presentation and paper will provide an overview of the initial WIPPS IRCM Suite and the important factors that were considered in defining the CAPS configuration.

Plutonium in the WIPP environment: its detection, distribution and behavior.

PubMed

Thakur, P; Ballard, S; Nelson, R

2012-05-01

The Waste Isolation Pilot Plant (WIPP) is the only operating deep underground geologic nuclear repository in the United States. It is located in southeastern New Mexico, approximately 655 m (2150 ft) below the surface of the Earth in a bedded Permian evaporite salt formation. This mined geologic repository is designed for the safe disposal of transuranic (TRU) wastes generated from the US defense program. Aerosol and soil samples have been collected near the WIPP site to investigate the sources of plutonium in the WIPP environment since the late 1990s, well before WIPP received its first shipment. Activities of (238)Pu, (239+240)Pu and (241)Am were determined by alpha spectrometry following a series of chemical separations. The concentrations of Al and U were determined in a separate set of samples by inductively coupled plasma mass spectrometry. The annual airborne concentrations of (239+240)Pu during the period from 1998 to 2010 show no systematic interannual variations. However, monthly (239+240)Pu particulate concentrations show a typical seasonal variation with a maximum in spring, the time when strong and gusty winds frequently give rise to blowing dust. Resuspension of soil particles containing weapons fallout is considered to be the predominant source of plutonium in the WIPP area. Further, this work characterizes the source, temporal variation and its distribution with depth in a soil profile to evaluate the importance of transport mechanisms affecting the fate of these radionuclides in the WIPP environment. The mean (137)Cs/(239+240)Pu, (241)Am/(239+240)Pu activity ratio and (240)Pu/(239)Pu atom ratio observed in the WIPP samples are consistent with the source being largely global fallout. There is no evidence of any release from the WIPP contributing to radionuclide concentrations in the environment.

WIPP Intermediate Scale Borehole Test. A pretest analysis

DOE Office of Scientific and Technical Information (OSTI.GOV)

Argueello, J.G.

A three-dimensional finite element structural analysis of the Intermediate Scale Borehole Test at the WIPP has been performed. The analysis provides insight into how a relatively new excavation in a creeping medium responds when introduced into an existing pillar which has been undergoing stress redistribution for 5.7 years. The stress field of the volume of material in the immediate vicinity of the borehole changes significantly when the hole is drilled. Closure of the hole is predicted to be larger in the vertical direction than in the horizontal direction, leading to an ovaling of the hole. The relatively high stresses nearmore » the hole persist even at the end of the simulation, 2 years after the hole is drilled.« less

WIPP

Science.gov Websites

waste Semi Truck with trailer hauling two TRUPACT-II containers Safely disposed of more than 170,000 waste containers WIPP has been disposing of legacy transuranic (TRU) waste since 1999, cleaning up 22 once waste... [January 17, 2018] read more... Semi Truck hauling three TRUPACT-II containers THE WIPP

Coupled Biological-Geomechanical-Geochemical Effects of the Disturbed Rock Zone on the Performance of the Waste Isolation Pilot Plant

NASA Astrophysics Data System (ADS)

Dunagan, S. C.; Herrick, C. G.; Lee, M. Y.

2008-12-01

The Waste Isolation Pilot Plant (WIPP) is located at a depth of 655 m in bedded salt in southeastern New Mexico and is operated by the U.S. Department of Energy as a deep underground disposal facility for transuranic (TRU) waste. The WIPP must comply with the EPA's environmental regulations that require a probabilistic risk analysis of releases of radionuclides due to inadvertent human intrusion into the repository at some time during the 10,000-year regulatory period. Sandia National Laboratories conducts performance assessments (PAs) of the WIPP using a system of computer codes representing the evolution of underground repository and emplaced TRU waste in order to demonstrate compliance. One of the important features modeled in a PA is the disturbed rock zone (DRZ) surrounding the emplacement rooms in the repository. The extent and permeability of DRZ play a significant role in the potential radionuclide release scenarios. We evaluated the phenomena occurring in the repository that affect the DRZ and their potential effects on the extent and permeability of the DRZ. Furthermore, we examined the DRZ's role in determining the performance of the repository. Pressure in the completely sealed repository will be increased by creep closure of the salt and degradation of TRU waste contents by microbial activity in the repository. An increased pressure in the repository will reduce the extent and permeability of the DRZ. The reduced DRZ extent and permeability will decrease the amount of brine that is available to interact with the waste. Furthermore, the potential for radionuclide release from the repository is dependent on the amount of brine that enters the repository. As a result of these coupled biological-geomechanical-geochemical phenomena, the extent and permeability of the DRZ has a significant impact on the potential radionuclide releases from the repository and, in turn, the repository performance. Sandia is a multi program laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy's National Nuclear Security Administration under Contract DE-AC04- 94AL85000. This research is funded by WIPP programs administered by the Office of Environmental Management (EM) of the U.S. Department of Energy.

Environmental assessment

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1995-08-01

The proposed overhead power line construction project (Sand Dunes to Ochoa, in Eddy and Lea Counties, New Mexico) will supply additional electric power to the Waste Isolation Pilot Plant (WIPP) and involve construction of a new electric substation at WIPP. This would provide a redundant electrical power source to WIPP. A finding of no significant impact is made.

Uranium (VI) solubility in carbonate-free ERDA-6 brine

DOE Office of Scientific and Technical Information (OSTI.GOV)

Lucchini, Jean-francois; Khaing, Hnin; Reed, Donald T

2010-01-01

When present, uranium is usually an element of importance in a nuclear waste repository. In the Waste Isolation Pilot Plant (WIPP), uranium is the most prevalent actinide component by mass, with about 647 metric tons to be placed in the repository. Therefore, the chemistry of uranium, and especially its solubility in the WIPP conditions, needs to be well determined. Long-term experiments were performed to measure the solubility of uranium (VI) in carbonate-free ERDA-6 brine, a simulated WIPP brine, at pC{sub H+} values between 8 and 12.5. These data, obtained from the over-saturation approach, were the first repository-relevant data for themore » VI actinide oxidation state. The solubility trends observed pointed towards low uranium solubility in WIPP brines and a lack of amphotericity. At the expected pC{sub H+} in the WIPP ({approx} 9.5), measured uranium solubility approached 10{sup -7} M. The objective of these experiments was to establish a baseline solubility to further investigate the effects of carbonate complexation on uranium solubility in WIPP brines.« less

Source and long-term behavior of transuranic aerosols in the WIPP environment.

PubMed

Thakur, P; Lemons, B G

2016-10-01

Source and long-term behavior transuranic aerosols ((239+240)Pu, (238)Pu, and (241)Am) in the ambient air samples collected at and near the Waste Isolation Pilot Plant (WIPP) deep geologic repository site were investigated using historical data from an independent monitoring program conducted by the Carlsbad Environmental Monitoring and Research Center and an oversight monitoring program conducted by the management and operating contractor for WIPP at and near the facility. An analysis of historical data indicates frequent detections of (239+240)Pu and (241)Am, whereas (238)Pu is detected infrequently. Peaks in (239+240)Pu and (241)Am concentrations in ambient air generally occur from March to June timeframe, which is when strong and gusty winds in the area frequently give rise to blowing dust. Long-term measurements of plutonium isotopes (1985-2015) in the WIPP environment suggest that the resuspension of previously contaminated soils is likely the primary source of plutonium in the ambient air samples from WIPP and its vicinity. There is no evidence that WIPP is a source of environmental contamination that can be considered significant by any health-based standard.

Characterization of the MVST waste tanks located at ORNL

DOE Office of Scientific and Technical Information (OSTI.GOV)

Keller, J.M.; Giaquinto, J.M.; Meeks, A.M.

During the fall of 1996 there was a major effort to sample and analyze the Active Liquid Low-Level Waste (LLLW) tanks at ORNL which include the Melton Valley Storage Tanks (MVST) and the Bethel Valley Evaporator Service Tanks (BVEST). The characterization data summarized in this report was needed to address waste processing options, address concerns of the performance assessment (PA) data for the Waste Isolation Pilot Plant (WIPP), evaluate the characteristics with respect to the waste acceptance criteria (WAC) for WIPP and Nevada Test Site (NTS), address criticality concerns, and meet DOT requirements for transporting the waste. This report onlymore » discusses the analytical characterization data for the MVST waste tanks. The isotopic data presented in this report support the position that fissile isotopes of uranium and plutonium were ``denatured`` as required by administrative controls. In general, MVST sludge was found to be both hazardous by RCRA characteristics and the transuranic alpha activity was well about the limit for TRU waste. The characteristics of the MVST sludge relative to the WIPP WAC limits for fissile gram equivalent, plutonium equivalent activity, and thermal power from decay heat, were estimated from the data in this report and found to be far below the upper boundary for any of the remote-handled transuranic waste requirements for disposal of the waste in WIPP.« less

Posttest analysis of a laboratory-cast monolith of salt-saturated concrete. Final report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Wakeley, L.D.; Poole, T.S.

A salt-saturated concrete was formulated for laboratory testing of cementitious mixtures with potential for use in disposal of radioactive wastes in a geologic repository in halite rock. Cores were taken from a laboratory-cast concrete monolith on completion of tests of permeability, strain, and stress. The cores were analyzed for physical and chemical evidence of brine migration through the concrete, and other features with potential impact on installation of crete plugs at the Waste Isolation Pilot Plant (WIPP) in New Mexico. The posttest analyses of the cores provided evidence of brine movement along the interface between concrete and pipe, and littlemore » indication of permeability through the monolith itself. There may also have been diffusion of chloride into the monolith without actual brine flow.« less

Biogeochemical Investigations to Evaluate the Performance of the Waste Isolation Pilot Plant (WIPP) (Invited)

NASA Astrophysics Data System (ADS)

Gillow, J. B.

2009-12-01

The Waste Isolation Pilot Plant (WIPP) is a U.S. Department of Energy facility located in southeastern New Mexico, approximately 655 m (2150 ft.) below ground surface in a bedded salt, Permian evaporite formation. This mined geologic repository has been receiving transuranic (TRU) waste from defense-related and environmental-management activities since March 1999. TRU waste contains alpha-emitting transuranic nuclides with half-lives greater than twenty years at concentrations greater than 100 nCi/gram. These actinide-contaminated wastes were generated from nuclear-weapons production and related processing activities. They include various organics, adsorbed liquids, sludges, cellulosics, plastics, rubber, and a variety of metals and cemented materials. An extensive set of investigations were performed to establish the basis for TRU waste disposal at WIPP and to support initial certification from the U.S. Environmental Protection Agency. A significant element of the conceptual geochemical model for WIPP is the microbiologically-driven reactions leading to biodegradation of organic constituents in TRU wastes, as well as interactions with actinides present in the waste. This presentation will discuss the biogeochemical investigations that were performed to evaluate microbiological activity at WIPP, including studies of gas generation due to biodegradation of cellulose, plastic, and rubber materials and actinide-microbe interactions leading to changes in actinide chemical speciation. Highlights of this work are discussed here. Cellulose biodegradation in salt-brine systems results in the generation of carbon dioxide and hydrogen, and aqueous fermentation products (low molecular weight organic acids). Hypersaline brine can limit the range of microbial metabolic pathways, due to the energetic stresses of maintaining osmotic balance compatible with metabolic processes. Methanogenesis yields the lowest free energy per mole of carbon and as such is often not detected in microorganisms that thrive in salt-brine environments (halophilic bacteria). However, laboratory tests performed over a period of 10 years demonstrated the production of methane gas from cellulose metabolism. Studies of actinide-microbe interactions revealed the bioaccumulation of uranium in phosphate-rich intracellular granules. These studies advanced the understanding of the metabolism of bacteria in salt-brine systems and the influence of halophilic microbiological activity on WIPP geochemistry.

No-migration variance petition. Appendices A--B: Volume 2, Revision 1

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1990-03-01

Volume II contains Appendix A, emergency plan and Appendix B, waste analysis plan. The Waste Isolation Pilot Plant (WIPP) Emergency plan and Procedures (WP 12-9, Rev. 5, 1989) provides an organized plan of action for dealing with emergencies at the WIPP. A contingency plan is included which is in compliance with 40 CFR Part 265, Subpart D. The waste analysis plan provides a description of the chemical and physical characteristics of the wastes to be emplaced in the WIPP underground facility. A detailed discussion of the WIPP Waste Acceptance Criteria and the rationale for its established units are also included.

Atmospheric Dispersion Modeling of the February 2014 Waste Isolation Pilot Plant Release

DOE Office of Scientific and Technical Information (OSTI.GOV)

Nasstrom, John; Piggott, Tom; Simpson, Matthew

2015-07-22

This report presents the results of a simulation of the atmospheric dispersion and deposition of radioactivity released from the Waste Isolation Pilot Plant (WIPP) site in New Mexico in February 2014. These simulations were made by the National Atmospheric Release Advisory Center (NARAC) at Lawrence Livermore National Laboratory (LLNL), and supersede NARAC simulation results published in a previous WIPP report (WIPP, 2014). The results presented in this report use additional, more detailed data from WIPP on the specific radionuclides released, radioactivity release amounts and release times. Compared to the previous NARAC simulations, the new simulation results in this report aremore » based on more detailed modeling of the winds, turbulence, and particle dry deposition. In addition, the initial plume rise from the exhaust vent was considered in the new simulations, but not in the previous NARAC simulations. The new model results show some small differences compared to previous results, but do not change the conclusions in the WIPP (2014) report. Presented are the data and assumptions used in these model simulations, as well as the model-predicted dose and deposition on and near the WIPP site. A comparison of predicted and measured radionuclide-specific air concentrations is also presented.« less

The Revised WIPP Passive Institutional Controls Program - A Conceptual Plan - 13145

DOE Office of Scientific and Technical Information (OSTI.GOV)

Patterson, Russ; Klein, Thomas; Van Luik, Abraham

2013-07-01

The Department of Energy/Carlsbad Field Office (DOE/CBFO) is responsible for managing all activities related to the disposal of TRU and TRU-mixed waste in the geologic repository, 650 m below the land surface, at WIPP, near Carlsbad, New Mexico. The main function of the Passive Institutional Controls (PIC's) program is to inform future generations of the long-lived radioactive wastes buried beneath their feet in the desert. For the first 100 years after cessation of disposal operations, the rooms are closed and the shafts leading underground sealed, WIPP is mandated by law to institute Active Institutional Controls (AIC's) with fences, gates, andmore » armed guards on patrol. At this same time a plan must be in place of how to warn/inform the future, after the AIC's are gone, of the consequences of intrusion into the geologic repository disposal area. A plan was put into place during the 1990's with records management and storage, awareness triggers, permanent marker design concepts and testing schedules. This work included the thoughts of expert panels and individuals. The plan held up under peer review and met the requirements of the U.S. Environmental Protection Agency (EPA). Today the NEA is coordinating a study called the 'Preservation of Records, Knowledge and Memory (RK and M) Across Generations' to provide the international nuclear waste repository community with a guide on how a nuclear record archive programs should be approached and developed. CBFO is cooperating and participating in this project and will take what knowledge is gained and apply that to the WIPP program. At the same time CBFO is well aware that the EPA and others are expecting DOE to move forward with planning for the future WIPP PIC's program; so a plan will be in place in time for WIPP's closure slated for the early 2030's. The DOE/CBFO WIPP PIC's program in place today meets the regulatory criteria, but complete feasibility of implementation is questionable, and may not be in conformance with the international guidance being developed. International guidance currently under development may suggest that the inter-generational equity principle strives to warn the future, however, in doing so not to unduly burden present generations. Building markers and monuments that are out of proportion to the risk being presented to the future is not in keeping with generational equity. With this in mind the DOE/CBFO is developing conceptual plans for re-evaluating and revising the current WIPP PIC's program. These conceptual plans will suggest scientific and technical work that must be completed to develop a 'new' PICs program that takes the best ideas of the present plan, blended with new ideas from the RK and M project, and proposed alternative permanent markers designs and materials in consideration. (authors)« less

WIPP (Waste Isolation Pilot Plant) intermediate scale borehole test: A pretest analysis

DOE Office of Scientific and Technical Information (OSTI.GOV)

Argueello, J.G.

A three-dimensional finite element structural analysis of the Intermediate Scale Borehole Test at the Waste Isolation Pilot Plant (WIPP) has been performed. The analysis provides insight into how a relatively new excavation in a creeping medium responds when introduced into an existing pillar which has been undergoing stress redistribution for 5.7 years. The stress field of the volume of material in the immediate vicinity of the borehole changes significantly when the hole is drilled. Closure of the hole is predicted to be larger in the vertical direction than in the horizontal direction, leading to an ovaling of the hole. Themore » relatively high stresses near the hole persist even at the end of the simulation, 2 years after the hole is drilled. 12 ref., 10 figs.« less

WIPP conceptual design report. Addendum A. Design calculations for Waste Isolation Pilot Plant (WIPP)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1977-04-01

The design calculations for the Waste Isolation Pilot Plant (WIPP) are presented. The following categories are discussed: general nuclear calculations; radwaste calculations; structural calculations; mechanical calculations; civil calculations; electrical calculations; TRU waste surface facility time and motion analysis; shaft sinking procedures; hoist time and motion studies; mining system analysis; mine ventilation calculations; mine structural analysis; and miscellaneous underground calculations.

FY15 Report on Thermomechanical Testing

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hansen, Francis D.; Buchholz, Stuart

2015-08-01

Sandia is participating in the third phase of a United States (US)-German Joint Project that compares constitutive models and simulation procedures on the basis of model calculations of the thermomechanical behavior and healing of rock salt (Salzer et al. 2015). The first goal of the project is to evaluate the ability of numerical modeling tools to correctly describe the relevant deformation phenomena in rock salt under various influences. Among the numerical modeling tools required to address this are constitutive models that are used in computer simulations for the description of the thermal, mechanical, and hydraulic behavior of the host rockmore » under various influences and for the long-term prediction of this behavior. Achieving this goal will lead to increased confidence in the results of numerical simulations related to the secure disposal of radioactive wastes in rock salt. Results of the Joint Project may ultimately be used to make various assertions regarding stability analysis of an underground repository in salt during the operating phase as well as long-term integrity of the geological barrier in the post-operating phase A primary evaluation of constitutive model capabilities comes by way of predicting large-scale field tests. The Joint Project partners decided to model Waste Isolation Pilot Plant (WIPP) Rooms B & D which are full-scale rooms having the same dimensions. Room D deformed under natural, ambient conditions while Room B was thermally driven by an array of waste-simulating heaters (Munson et al. 1988; 1990). Existing laboratory test data for WIPP salt were carefully scrutinized and the partners decided that additional testing would be needed to help evaluate advanced features of the constitutive models. The German partners performed over 140 laboratory tests on WIPP salt at no charge to the US Department of Energy (DOE).« less

Effects of microbial processes on gas generation under expected WIPP repository conditions: Annual report through 1992

DOE Office of Scientific and Technical Information (OSTI.GOV)

Francis, A.J.; Gillow, J.B.

1993-09-01

Microbial processes involved in gas generation from degradation of the organic constituents of transuranic waste under conditions expected at the Waste Isolation Pilot Plant (WIPP) repository are being investigated at Brookhaven National Laboratory. These laboratory studies are part of the Sandia National Laboratories -- WIPP Gas Generation Program. Gas generation due to microbial degradation of representative cellulosic waste was investigated in short-term (< 6 months) and long-term (> 6 months) experiments by incubating representative paper (filter paper, paper towels, and tissue) in WIPP brine under initially aerobic (air) and anaerobic (nitrogen) conditions. Samples from the WIPP surficial environment and undergroundmore » workings harbor gas-producing halophilic microorganisms, the activities of which were studied in short-term experiments. The microorganisms metabolized a variety of organic compounds including cellulose under aerobic, anaerobic, and denitrifying conditions. In long-term experiments, the effects of added nutrients (trace amounts of ammonium nitrate, phosphate, and yeast extract), no nutrients, and nutrients plus excess nitrate on gas production from cellulose degradation.« less

The Waste Isolation Pilot Plant transuranic waste repository: A sleeping beauty

DOE Office of Scientific and Technical Information (OSTI.GOV)

Eriksson, L.G.

On May 13, 1998, crowning a 24-year United States Department of Energy effort, the US Environmental Protection Agency certified that the deep geological repository for safe disposal of long-lived, transuranic radioactive waste proposed by the DOE at the Waste Isolation Pilot Plant site in New Mexico complied with all applicable environmental radiation protection standards and compliance criteria. Pursuant to the applicable law, the WIPP Land Withdrawal Act of 1992, as amended in 1997, at the decision of the secretary of energy, the WIPP repository could open 30 calendar days after receiving the EPA certification. The secretary of energy announced Maymore » 13, 1998, that he intended to open the WIPP TRUW repository by June 14, 1998. However, at the end of 1998, the opening of the WIPP TRUW repository remains hostage to time-consuming, hazardous-waste-permitting procedures by the state of New Mexico Environment Department and two legal actions. Based on the EPA-verified high safety and the demonstrated risk reduction to both current and future generations offered by the WIPP TRUW repository, it is concluded that the WIPP TRUW repository is a sleeping beauty that will awake, perhaps in stages, and begin its important mission in 1999.« less

Analysis of Waste Isolation Pilot Plant Samples: Integrated Summary Report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Britt, Phillip F

2015-03-01

Analysis of Waste Isolation Pilot Plant Samples: Integrated Summary Report. Summaries of conclusions, analytical processes, and analytical results. Analysis of samples taken from the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico in support of the WIPP Technical Assessment Team (TAT) activities to determine to the extent feasible the mechanisms and chemical reactions that may have resulted in the breach of at least one waste drum and release of waste material in WIPP Panel 7 Room 7 on February 14, 2014. This report integrates and summarizes the results contained in three separate reports, described below, and draws conclusions basedmore » on those results. Chemical and Radiochemical Analyses of WIPP Samples R-15 C5 SWB and R16 C-4 Lip; PNNL-24003, Pacific Northwest National Laboratory, December 2014 Analysis of Waste Isolation Pilot Plant (WIPP) Underground and MgO Samples by the Savannah River National Laboratory (SRNL); SRNL-STI-2014-00617; Savannah River National Laboratory, December 2014 Report for WIPP UG Sample #3, R15C5 (9/3/14); LLNL-TR-667015; Lawrence Livermore National Laboratory, January 2015 This report is also contained in the Waste Isolation Pilot Plant Technical Assessment Team Report; SRNL-RP-2015-01198; Savannah River National Laboratory, March 17, 2015, as Appendix C: Analysis Integrated Summary Report.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Chace, D.A.; Roberts, R.M.; Palmer, J.B.

WIPP Salado Hydrology Program Data Report {number_sign}3 presents hydrologic data collected during permeability testing, coupled permeability and hydrofracture testing, and gas-threshold-pressure testing of the Salado Formation performed from November 1991 through October 1995. Fluid-pressure monitoring data representing August 1989 through May 1995 are also included. The report presents data from the drilling and testing of three boreholes associated with the permeability testing program, nine boreholes associated with the coupled permeability and hydrofracture testing program, and three boreholes associated with the gas-threshold-pressure testing program. The purpose of the permeability testing program was to provide data with which to interpret the disturbedmore » and undisturbed permeability and pore pressure characteristics of the different Salado Formation lithologies. The purpose of the coupled permeability and hydrofracture testing program was to provide data with which to characterize the occurrence, propagation, and direction of pressure induced fractures in the Salado Formation lithologies, especially MB139. The purpose of the gas-threshold-pressure testing program was to provide data with which to characterize the conditions under which pressurized gas displaces fluid in the brine-saturated Salado Formation lithologies. All of the holes were drilled from the WIPP underground facility 655 m below ground surface in the Salado Formation.« less

Environmental Assessment for the Above Ground Storage Capability at the Waste Isolation Pilot Plant Draft

DOE Office of Scientific and Technical Information (OSTI.GOV)

None, None

The Waste Isolation Pilot Plant (WIPP) is the nation’s only approved repository for the disposal of defense related/defense generated transuranic (TRU) and mixed hazardous TRU waste (henceforth called TRU waste). The mission of the WIPP Project is to realize the safe disposal of TRU waste from TRU waste generator sites in the Department of Energy waste complex. The WIPP Project was authorized by Title II, Section 213(a) of Public Law 96-164 (U. S. Congress 1979). Congress designated the WIPP facility “for the express purpose of providing a research and development facility to demonstrate the safe disposal of radioactive wastes resultingmore » from the defense activities and programs of the United States exempted from regulation by the Nuclear Regulatory Commission (NRC).” The WIPP facility is operated by the U. S. Department of Energy (DOE). Transuranic waste that is disposed in the WIPP facility is defined by Section 2(18) the WIPP Land Withdrawal Act of 1992 (LWA) (U. S. Congress, 1992) as: “waste containing more than 100 nanocuries of alpha-emitting transuranic isotopes per gram of waste, with half-lives greater than 20 years, except for: (A) high-level radioactive waste; (B) waste that the Secretary has determined, with the concurrence of the Administrator, does not need the degree of isolation required by the disposal regulations; or (C) waste that the NRC has approved for disposal on a case-by-case basis in accordance with part 61 of title 10, Code of Federal Regulations (CFR).« less

Pretest reference calculation for the 6. 1 meter (20 ft) wide drifts of the Geomechanical Evaluation (WIPP Room G in situ experiment)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Morgan, H.S.; Stone, C.M.

A pretest reference calculation for the Geomechanical Evaluation or Room G experiment is presented. The Geomechanical Evaluation is one of several large-scale in situ tests currently under construction near Carlsbad, New Mexico, at the site of the Waste Isolation Pilot Plant (WIPP). The Room G experiment consists of isolated, two-dimensional drifts with different room spans, an isolated drift intersection, and a wedge pillar. The primary purpose of the experiment is to provide data for validating computational modeling capabilities used in analyzing nuclear waste repositories in salt. The calculation presented here addresses only one portion of the test, namely isolated driftmore » configurations which are initially 6.1 m (20 ft) wide by 3.05 m (10 ft) high. The Geomechanical Evaluation is heavily instrumented for monitoring deformations due to creep of the salt. Data from the experiment are not available at the present time, but the measurements for Room G will eventually be compared to the results presented in this report to assess and improve structural modeling capabilities for the WIPP. The model used for this calculation represents the state of the art at the present time. A large number of plots are included since an appropriate result is presented for every gage location associated with the 6.1 m wide drifts. 53 refs., 53 figs., 3 tabs.« less

Pretest reference calculation for the Heated Axisymmetric Pillar (WIPP Room H in situ experiment)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Morgan, H.S.; Stone, C.M.

A pretest reference calculation for the Heated Axisymmetric Pillar or Room H experiment is presented in this report. The Heated Axisymmetric Pillar is one of several large scale in situ experiments currently under construction near Carlsbad, New Mexico, at the site of the Waste Isolation Pilot Plant (WIPP). This test is an intermediate step in validating numerical techniques for design and performance calculations for radioactive waste repositories in salt. The test consists of a cylindrically shaped pillar, centrally located in an annular drift, which is uniformly heated by blanket heaters. These heaters produce a thermal output of 135 W/m/sup 2/.more » This load will be supplied for a period of three years. Room H is heavily instrumented for monitoring both temperature increases due to the thermal loading and deformations due to creep of the salt. Data from the experiment are not available at the present time, but the measurements for Room H will eventually be compared to the calculation presented in this report to assess and improve thermal and mechanical modeling capabilities for the WIPP. The thermal/structural model used in the calculation represents the state of the art at the present time. A large number of plots are included since an appropriate result is required for every Room H gauge location. 56 refs., 97 figs., 4 tabs.« less

Adjunct laboratory tests in support of US/German salt characterization program

DOE Office of Scientific and Technical Information (OSTI.GOV)

Buchholz, Stuart A.

2014-07-01

In summary, the goal of this activity is to complete a subset of a test matrix on salt from the Waste Isolation Pilot Plant (WIPP) undertaken by German research groups. The work will be performed at RESPEC in Rapid City, South Dakota, and is divided into three tasks.

WIPP Pecos Management Reports

EPA Pesticide Factsheets

These reviews and evaluations compiled by Pecos Management Services, Inc. encompass the current and future WIPP activities in the program areas of TRU waste characterization, transportation, and disposal.

The densities of halite-saturated WIPP-A and NBT-6 brines and their NaCl contents in weight percent, molal, and molar units from 20 to 100 degrees C

USGS Publications Warehouse

Chou, I-Ming; Buizinga, B.; Clynne, M.A.; Potter, R.W.

1982-01-01

A series of density measurements has been performed at 30?, 50?, 70?, and 90?C for halite-undersaturated WIPP-A and NBT-6 brines with various NaCl contents approaching saturation. The densities of halite-saturated WIPP-A and NBT-6 brines were obtained by extrapolating these measured densities to halite saturation points. The maximum difference between the densities obtained in this Fashion and those calculated from the model of Potter and Haas is 0.015 g/cm3. The NaCl contents in halite-saturated WIPP-A and NBT-6 brines are reported in wt %, molal, and molar units from 20? to 100?C.

Geohydrology of the proposed Waste Isolation Pilot Plant site, Los Medanos area, southeastern New Mexico

USGS Publications Warehouse

Mercer, Jerry W.

1983-01-01

Geohydrologic data have been collected in the Los Medanos area at the U.S. Department of Energy 's proposed Waste Isolation Pilot Plant (WIPP) site in southeastern New Mexico since 1975 as part of an intensive study evaluating the feasibility of storing defense-associated nuclear wastes within the bedded salt of the Salado Formation of Permian age. Drilling and hydrologic testing have identified three principal water-producing zones above the salt, including the Rustler-Salado Formational contact and the Culebra and Magenta Dolomite Members of the Permian Rustler Formation. Below the bedded salt there is another water-bearing zone, the channel sandstones of the Bell Canyon formation of the Permian Delaware Mountain Group. Most data collected from 33 hydrologic test holes indicate that the water-bearing zones are characterized by low transmissivities and contain slightly saline to briny water. Data collected from drill-stem tests in the Bell Canyon Formation indicate the channel sandstones have hydraulic conductivities ranging from 0.02 to 0.36 feet per day grade vertically and laterally into siltstones and shales of very low permeability. The Rustler Formation contains the principal water-producing zones identified at the WIPP site. The Rustler-Salado formational contact has the least transmissivity, ranging from 0.00003 to 0.003 feet squared per day. The Culebra Dolomite is the most productive unit at the WIPP site with transmissivities ranging from 0.001 to 73 feet squared per day; the greater values result from fracturing in the dolomite created by dissolution of underlying halite. Minute vertical permeabilities prevent movement of water between hydrologic units. (USGS)

Waste Isolation Pilot Plant No-migration variance petition. Addendum: Volume 7, Revision 1

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1990-03-01

This report describes various aspects of the Waste Isolation Pilot Plant (WIPP) including design data, waste characterization, dissolution features, ground water hydrology, natural resources, monitoring, general geology, and the gas generation/test program.

Pit 9 Category of Transuranic Waste Stored Below Ground within Area G

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hargis, Kenneth M.

2014-01-08

A large wildfire called the Las Conchas Fire burned large areas near Los Alamos National Laboratory (LANL) in 2011 and heightened public concern and news media attention over transuranic (TRU) waste stored at LANL’s Technical Area 54 (TA-54) Area G waste management facility. The removal of TRU waste from Area G had been placed at a lower priority in budget decisions for environmental cleanup at LANL because TRU waste removal is not included in the March 2005 Compliance Order on Consent (Reference 1) that is the primary regulatory driver for environmental cleanup at LANL. The Consent Order is an agreementmore » between LANL and the New Mexico Environment Department (NMED) that contains specific requirements and schedules for cleaning up historical contamination at the LANL site. After the Las Conchas Fire, discussions were held by the U.S. Department of Energy (DOE) with the NMED on accelerating TRU waste removal from LANL and disposing it at the Waste Isolation Pilot Plant (WIPP).This report summarizes available information on the origin, configuration, and composition of the waste containers within Pit 9, their physical and radiological characteristics, and issues that may be encountered in their retrieval and processing. Review of the available information indicates that Pit 9 should present no major issues in retrieval and processing, and most drums contain TRU waste that can be shipped to WIPP. The primary concern in retrieval is the integrity of containers that have been stored below-ground for 35 to 40 years. The most likely issue that will be encountered in processing containers retrieved from Pit 9 is the potential for items that are prohibited at WIPP such as sealed containers greater than four liters in size and free liquids that exceed limits for WIPP.« less

Waste Isolation Pilot Plant Biennial Environmental Compliance Report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Westinghouse TRU Solutions

This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 1998, to March 31, 2000. As required by the WIPP Land Withdrawal Act (LWA)(Public Law [Pub. L.] 102-579, and amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) Carlsbad Area Office's (hereinafter the ''CAO'') compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico. An issue was identified inmore » the 1998 BECR relating to a potential cross-connection between the fire-water systems and the site domestic water system. While the CAO and its managing and operating contractor (hereinafter the ''MOC'') believe the site was always in compliance with cross-connection control requirements, hardware and procedural upgrades w ere implemented in March 1999 to strengthen its compliance posture. Further discussion of this issue is presented in section 30.2.2 herein. During this reporting period WIPP received two letters and a compliance order alleging violation of certain requirements outlined in section 9(a)(1) of the LWA. With the exception of one item, pending a final decision by the New Mexico Environment Department (NMED), all alleged violations have been resolved without the assessment of fines or penalties. Non-mixed TRU waste shipments began on March 26, 1999. Shipments continued through November 26, 1999, the effective date of the Waste Isolation Pilot Plant Hazardous Waste Facility Permit (NM4890139088-TSDF). No shipments regulated under the Hazardous Waste Facility Permit were received at WIPP during this BECR reporting period.« less

Analysis of EPA and DOE WIPP Air Sampling Data

EPA Pesticide Factsheets

During the April 2014 EPA visit to WIPP, EPA co-located four ambient air samplers with existing Department of Energy (DOE) ambient air samplers to independently corroborate DOE's reported air sampling results.

AIR DISPERSION MODELING AT THE WASTE ISOLATION PILOT PLANT

DOE Office of Scientific and Technical Information (OSTI.GOV)

Rucker, D.F.

2000-08-01

One concern at the Waste Isolation Pilot Plant (WIPP) is the amount of alpha-emitting radionuclides or hazardous chemicals that can become airborne at the facility and reach the Exclusive Use Area boundary as the result of a release from the Waste Handling Building (WHB) or from the underground during waste emplacement operations. The WIPP Safety Analysis Report (SAR), WIPP RCRA Permit, and WIPP Emergency Preparedness Hazards Assessments include air dispersion calculations to address this issue. Meteorological conditions at the WIPP facility will dictate direction, speed, and dilution of a contaminant plume of respirable material due to chronic releases or duringmore » an accident. Due to the paucity of meteorological information at the WIPP site prior to September 1996, the Department of Energy (DOE) reports had to rely largely on unqualified climatic data from the site and neighboring Carlsbad, which is situated approximately 40 km (26 miles) to the west of the site. This report examines the validity of the DOE air dispersion calculations using new meteorological data measured and collected at the WIPP site since September 1996. The air dispersion calculations in this report include both chronic and acute releases. Chronic release calculations were conducted with the EPA-approved code, CAP88PC and the calculations showed that in order for a violation of 40 CFR61 (NESHAPS) to occur, approximately 15 mCi/yr of 239Pu would have to be released from the exhaust stack or from the WHB. This is an extremely high value. Hence, it is unlikely that NESHAPS would be violated. A site-specific air dispersion coefficient was evaluated for comparison with that used in acute dose calculations. The calculations presented in Section 3.2 and 3.3 show that one could expect a slightly less dispersive plume (larger air dispersion coefficient) given greater confidence in the meteorological data, i.e. 95% worst case meteorological conditions. Calculations show that dispersion will decrease slightly if a more stable wind class is assumed, where very little vertical mixing occurs. It is recommended that previous reports which used fixed values for calculating the air dispersion coefficient be updated to reflect the new meteorological data, such as the WIPP Safety Analysis Report and the WIPP Emergency Preparedness Hazards Assessment. It is also recommended that uncertainty be incorporated into the calculations so that a more meaningful assessment of risk during accidents can be achieved.« less

Weatherization Innovation Pilot Program: Program Overview and Philadelphia Project Highlight (Fact Sheet)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

2012-01-01

Case Study with WIPP program overview, information regarding eligibility, and successes from Pennsylvania's Commission on Economic Opportunity (CEO) that demonstrate innovative approaches that maximize the benefit of the program. The Department of Energy (DOE) Office of Energy Efficiency and Renewable Energy (EERE) recently launched the Weatherization Innovation Pilot Program (WIPP) to accelerate innovations in whole-house weatherization and advance DOE's goal of increasing the energy efficiency and health and safety of homes of low-income families. Since 2010, WIPP has helped weatherization service providers as well as new and nontraditional partners leverage non-federal financial resources to supplement federal grants, saving taxpayer money.more » WIPP complements the Weatherization Assistance program (WAP), which operates nation-wide, in U.S. territories and in three Native American tribes. 16 grantees are implementing weatherization innovation projects using experimental approaches to find new and better ways to weatherize homes. They are using approaches such as: (1) Financial tools - by understanding a diverse range of financing mechanisms, grantees can maximize the impact of the federal grant dollars while providing high-quality work and benefits to eligible low-income clients; (2) Green and healthy homes - in addition to helping families reduce their energy costs, grantees can protect their health and safety. Two WIPP projects (Connecticut and Maryland) will augment standard weatherization services with a comprehensive green and healthy homes approach; (3) New technologies and techniques - following the model of continuous improvement in weatherization, WIPP grantees will continue to use new and better technologies and techniques to improve the quality of work; (4) Residential energy behavior change - Two grantees are rigorously testing home energy monitors (HEMs) that display energy used in kilowatt-hours, allowing residents to monitor and reduce their energy use, and another is examining best-practices for mobile home energy efficiency; (5) Workforce development and volunteers - with a goal of creating a self-sustaining weatherization model that does not require future federal investment, three grantees are adapting business models successful in other sectors of the home performance business to perform weatherization work. Youthbuild is training youth to perform home energy upgrades to eligible clients and Habitat for Humanity is developing a model for how to incorporate volunteer labor in home weatherization. These innovative approaches will improve key weatherization outcomes, such as: Increasing the total number of homes that are weatherized; Reducing the weatherization cost per home; Increasing the energy savings in each weatherized home; Increasing the number of weatherization jobs created and retained; and Reducing greenhouse gas emissions.« less

NDA BATCH 2002-02

DOE Office of Scientific and Technical Information (OSTI.GOV)

Lawrence Livermore National Laboratory

2009-12-09

QC sample results (daily background checks, 20-gram and 100-gram SGS drum checks) were within acceptable criteria established by WIPP's Quality Assurance Objectives for TRU Waste Characterization. Replicate runs were performed on 5 drums with IDs LL85101099TRU, LL85801147TRU, LL85801109TRU, LL85300999TRU and LL85500979TRU. All replicate measurement results are identical at the 95% confidence level as established by WIPP criteria. Note that the batch covered 5 weeks of SGS measurements from 23-Jan-2002 through 22-Feb-2002. Data packet for SGS Batch 2002-02 generated using gamma spectroscopy with the Pu Facility SGS unit is technically reasonable. All QC samples are in compliance with established control limits.more » The batch data packet has been reviewed for correctness, completeness, consistency and compliance with WIPP's Quality Assurance Objectives and determined to be acceptable. An Expert Review was performed on the data packet between 28-Feb-02 and 09-Jul-02 to check for potential U-235, Np-237 and Am-241 interferences and address drum cases where specific scan segments showed Se gamma ray transmissions for the 136-keV gamma to be below 0.1 %. Two drums in the batch showed Pu-238 at a relative mass ratio more than 2% of all the Pu isotopes.« less

Environmental assessment of the Carlsbad Environmental Monitoring and Research Center Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1995-10-01

This Environmental Assessment has been prepared to determine if the Carlsbad Environmental Monitoring and Research Center (the Center), or its alternatives would have significant environmental impacts that must be analyzed in an Environmental Impact Statement. DOE`s proposed action is to continue funding the Center. While DOE is not funding construction of the planned Center facility, operation of that facility is dependent upon continued funding. To implement the proposed action, the Center would initially construct a facility of approximately 2,300 square meters (25,000 square feet). The Phase 1 laboratory facilities and parking lot will occupy approximately 1.2 hectares (3 acres) ofmore » approximately 8.9 hectares (22 acres) of land which were donated to New Mexico State University (NMSU) for this purpose. The facility would contain laboratories to analyze chemical and radioactive materials typical of potential contaminants that could occur in the environment in the vicinity of the DOE Waste Isolation Pilot Plant (WIPP) site or other locations. The facility also would have bioassay facilities to measure radionuclide levels in the general population and in employees of the WIPP. Operation of the Center would meet the DOE requirement for independent monitoring and assessment of environmental impacts associated with the planned disposal of transuranic waste at the WIPP.« less

Waste Isolation Pilot Plant Salt Decontamination Testing

DOE Office of Scientific and Technical Information (OSTI.GOV)

Demmer, Ricky Lynn; Reese, Stephen Joseph

2015-03-01

On February 14, 2014, americium and plutonium contamination was released in the Waste Isolation Pilot Plant (WIPP) salt caverns. Several practical, easily deployable methods of decontaminating WIPP salt, using a surrogate contaminant and americium (241Am), were developed and tested. The effectiveness of the methods is evaluated qualitatively, and to the extent practical, quantitatively. Of the methods tested (dry brushing, vacuum cleaning, water washing, mechanical grinding, strippable coatings, and fixative barriers), the most practical seems to be water washing. Effectiveness is very high, and water washing is easy and rapid to deploy. The amount of wastewater produced (~2 L/m2) would bemore » substantial and may not be easy to manage, but the method is the clear winner from a usability perspective. Removable surface contamination levels (smear results) from water washed coupons found no residual removable contamination. Thus, whatever contamination is left is likely adhered to (or trapped within) the salt. The other option that shows promise is the use of a fixative barrier. Bartlett Nuclear, Inc.’s Polymeric Barrier System proved the most durable of the coatings tested. The coatings were not tested for contaminant entrapment, only for coating integrity and durability.« less

Leveraging Radioactive Waste Disposal at WIPP for Science

NASA Astrophysics Data System (ADS)

Rempe, N. T.

2008-12-01

Salt mines are radiologically much quieter than other underground environments because of ultra-low concentrations of natural radionuclides (U, Th, and K) in the host rock; therefore, the Waste Isolation Pilot Plant (WIPP), a government-owned, 655m deep geologic repository that disposes of radioactive waste in thick salt near Carlsbad, New Mexico, has for the last 15 years hosted highly radiation-sensitive experiments. Incidentally, Nature started her own low background experiment 250ma ago, preserving viable bacteria, cellulose, and DNA in WIPP salt. The Department of Energy continues to make areas of the WIPP underground available for experiments, freely offering its infrastructure and access to this unique environment. Even before WIPP started disposing of waste in 1999, the Room-Q alcove (25m x 10m x 4m) housed a succession of small experiments. They included development and calibration of neutral-current detectors by Los Alamos National Laboratory (LANL) for the Sudbury Neutrino Observatory, a proof-of-concept by Ohio State University of a flavor-sensitive neutrino detector for supernovae, and research by LANL on small solid- state dark matter detectors. Two currently active experiments support the search for neutrino-less double beta decay as a tool to better define the nature and mass of the neutrino. That these delicate experiments are conducted in close vicinity to, but not at all affected by, megacuries of radioactive waste reinforces the safety argument for the repository. Since 2003, the Majorana collaboration is developing and testing various detector designs inside a custom- built clean room in the Room-Q alcove. Already low natural background readings are reduced further by segmenting the germanium detectors, which spatially and temporally discriminates background radiation. The collaboration also demonstrated safe copper electro-forming underground, which minimizes cosmogenic background in detector assemblies. The largest currently used experimental space (100m x 10m x 6m) is the North Experimental Area (NExA). There, Enriched Xenon Observatory (EXO) collaborators have since mid-2007 been assembling and outfitting six modules and associated structures that were pre-assembled at Stanford University, then dismantled, and shipped to WIPP. Transporting the modules underground presented several interesting challenges, all of which were overcome. Access through increasingly cleaner joined modules leads to the class-100 clean room detector module. Inside, a time projection chamber (TPC) contains 200kg liquid Xe- 136 (the largest non-defense related stockpile of an enriched isotope ever assembled for research). After the experiment starts in early 2009, it is expected to run for 3-5 years. University of Pennsylvania researchers recently sampled WIPP salt to attempt measuring stable Ne-22, resulting from the interaction of cosmogenic muons with Na-23 and preserved in the halite lattice, to determine variations in the cosmic-radiation flux. They in turn could reveal the history of nearby supernovae. University of Chicago/Fermilab researchers evaluate whether to install a superheated-fluid bubble-chamber to search for weakly interacting massive particles (WIMPs). A helium-filled solar neutrino TPC, dark matter and neutron detectors, and proton-decay and supernova-neutrino detectors are other projects that were and are under discussion. Rounding out the spectrum of possibilities are experiments to investigate the effects of long-term ultra-low-dose radiation on cell cultures and laboratory animals to verify or falsify the linear, no- threshold hypothesis. WIPP welcomes additional proposals and projects.

Quality quandaries: Statistical detective work to understand the isotopic ratios in Drum 68660 and the radioactive release at WIPP

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kelly, Elizabeth J.; Weaver, Brian Phillip; Veirs, Douglas Kirk

An incident at the Department of Energy's Waste Isolation Pilot Plant (WIPP) in 2014 resulted in the release of radioactive material into the environment. Initially, it was known that at least one drum in WIPP, identified as drum 68660, was involved. However, questions remained. Could the air-monitor isotopic ratios measured in WIPP at the time of the release be explained by materials in drum 68660 or were other drums involved? Could internal conditions in drum 68660 have caused the breach? What were the implications for 68660's sister drum? These questions needed to be answered as quickly as possible. Here, thismore » analysis, which was completed in three weeks, combined combinatorics and uncertainty analysis to provide scientists with the timely evidence they needed to either answer these important questions or to design experiments to answer them.« less

Quality quandaries: Statistical detective work to understand the isotopic ratios in Drum 68660 and the radioactive release at WIPP

DOE PAGES

Kelly, Elizabeth J.; Weaver, Brian Phillip; Veirs, Douglas Kirk

2017-08-09

An incident at the Department of Energy's Waste Isolation Pilot Plant (WIPP) in 2014 resulted in the release of radioactive material into the environment. Initially, it was known that at least one drum in WIPP, identified as drum 68660, was involved. However, questions remained. Could the air-monitor isotopic ratios measured in WIPP at the time of the release be explained by materials in drum 68660 or were other drums involved? Could internal conditions in drum 68660 have caused the breach? What were the implications for 68660's sister drum? These questions needed to be answered as quickly as possible. Here, thismore » analysis, which was completed in three weeks, combined combinatorics and uncertainty analysis to provide scientists with the timely evidence they needed to either answer these important questions or to design experiments to answer them.« less

WIPP Repository Reconfiguration

EPA Pesticide Factsheets

On August 30, 2011, the U.S. Department of Energy (DOE) provided a proposed planned change request that will relocate Panels 9 and 10 from the main north-south access drifts to south of the existing Panels 4 and 5 in the WIPP repository.

Source term estimation and the isotopic ratio of radioactive material released from the WIPP repository in New Mexico, USA.

PubMed

Thakur, P

2016-01-01

After almost 15 years of operations, the Waste Isolation Pilot Plant (WIPP) had one of its waste drums breach underground as a result of a runaway chemical reaction in the waste it contained. This incident occurred on February 14, 2014. Moderate levels of radioactivity were released into the underground air. A small portion of the contaminated underground air also escaped to the surface through the ventilation system and was detected approximately 1 km away from the facility. According to the source term estimation, the actual amount of radioactivity released from the WIPP site was less than 1.5 mCi. The highest activity detected on the surface was 115.2 μBq/m(3) for (241)Am and 10.2 μBq/m(3) for (239+240)Pu at a sampling station located 91 m away from the underground air exhaust point and 81.4 μBq/m(3) of (241)Am and 5.8 μBq/m(3) of (239+240)Pu at a monitoring station located approximately 1 km northwest of the WIPP facility. The dominant radionuclides released were americium and plutonium, in a ratio that matches the content of the breached drum. Air monitoring across the WIPP site intensified following the first reports of radiation detection underground to determine the extent of impact to WIPP personnel, the public, and the environment. In this paper, the early stage monitoring data collected by an independent monitoring program conducted by the Carlsbad Environmental Monitoring & Research Center (CEMRC) and an oversight monitoring program conducted by the WIPP's management and operating contractor, the Nuclear Waste Partnership (NWP) LLC were utilized to estimate the actual amount of radioactivity released from the WIPP underground. The Am and Pu isotope ratios were measured and used to support the hypothesis that the release came from one drum identified as having breached that represents a specific waste stream with this radionuclide ratio in its inventory. This failed drum underwent a heat and gas producing reaction that overpowered its vent and lifted its lid to allow release of waste into the underground air. Copyright © 2015 Elsevier Ltd. All rights reserved.

WIPP Docket A-93-02

EPA Pesticide Factsheets

WIPP Docket No. A-93-02 contains information that EPA considered in making its 1998 decision to certify that the Department of Energy had met the compliance criteria established by 40 CFR Part 194 and disposal regulations set by 40 CFR Part 191.

Environmental analysis Waste Isolation Pilot Plant (WIPP) cost reduction proposals

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

The Waste Isolation Pilot Plant (WIPP) is a research and development facility to demonstrate the safe disposal of radioactive wastes resulting from the defense activities and programs of the United States government. The facility is planned to be developed in bedded salt at the Los Medanos site in southeastern New Mexico. The environmental consequences of contruction and operation of the WIPP facility are documented in ''Final Environmental Impact Statement, Waste Isolation Pilot Plant''. The proposed action addressed by this environmental analysis is to simplify and reduce the scope of the WIPP facility as it is currently designed. The proposed changesmore » to the existing WIPP design are: limit the waste storage rate to 500,000 cubic feet per year; eliminate one shaft and revise the underground ventilation system; eliminate the underground conveyor system; combine the Administration Building, the Underground Personnel Building and the Waste Handling Building office area; simplify the central monitoring system; simplify the security control systems; modify the Waste Handling Building; simplify the storage exhaust system; modify the above ground salt handling logistics; simplify the power system; reduce overall site features; simplify the Warehouse/Shops Building and eliminate the Vehicle Maintenance Building; and allow resource recovery in Control Zone IV.« less

Evaluation of methods for measuring relative permeability of anhydride from the Salado Formation: Sensitivity analysis and data reduction

DOE Office of Scientific and Technical Information (OSTI.GOV)

Christiansen, R.L.; Kalbus, J.S.; Howarth, S.M.

This report documents, demonstrates, evaluates, and provides theoretical justification for methods used to convert experimental data into relative permeability relationships. The report facilities accurate determination of relative permeabilities of anhydride rock samples from the Salado Formation at the Waste Isolation Pilot Plant (WIPP). Relative permeability characteristic curves are necessary for WIPP Performance Assessment (PA) predictions of the potential for flow of waste-generated gas from the repository and brine flow into repository. This report follows Christiansen and Howarth (1995), a comprehensive literature review of methods for measuring relative permeability. It focuses on unsteady-state experiments and describes five methods for obtaining relativemore » permeability relationships from unsteady-state experiments. Unsteady-state experimental methods were recommended for relative permeability measurements of low-permeability anhydrite rock samples form the Salado Formation because these tests produce accurate relative permeability information and take significantly less time to complete than steady-state tests. Five methods for obtaining relative permeability relationships from unsteady-state experiments are described: the Welge method, the Johnson-Bossler-Naumann method, the Jones-Roszelle method, the Ramakrishnan-Cappiello method, and the Hagoort method. A summary, an example of the calculations, and a theoretical justification are provided for each of the five methods. Displacements in porous media are numerically simulated for the calculation examples. The simulated product data were processed using the methods, and the relative permeabilities obtained were compared with those input to the numerical model. A variety of operating conditions were simulated to show sensitivity of production behavior to rock-fluid properties.« less

OE-WIPP Event Presentation

DOE Office of Scientific and Technical Information (OSTI.GOV)

Erickson, Randall Mark

Information is given on waste generation at TA-55 and remediation needed to meet WIPP acceptance criteria, including the role of nitrate salts. Breaching of a particular waste-filled drum is reviewed, along with an accident analysis and steps for corrective actions and improved process management.

75 FR 41421 - Notification of Completeness of the Department of Energy's Compliance Recertification Application...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-07-16

... (CRA or ``application'') for the Waste Isolation Pilot Plant (WIPP) is complete. EPA provided written... disposal regulations. EPA is now engaged in the full technical review that will determine if WIPP remains... technical difficulties and cannot contact [[Page 41422

Uncertainty and sensitivity analysis for two-phase flow in the vicinity of the repository in the 1996 performance assessment for the Waste Isolation Pilot Plant: Disturbed conditions

DOE Office of Scientific and Technical Information (OSTI.GOV)

HELTON,JON CRAIG; BEAN,J.E.; ECONOMY,K.

2000-05-22

Uncertainty and sensitivity analysis results obtained in the 1996 performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP) are presented for two-phase flow in the vicinity of the repository under disturbed conditions resulting from drilling intrusions. Techniques based on Latin hypercube sampling, examination of scatterplots, stepwise regression analysis, partial correlation analysis and rank transformations are used to investigate brine inflow, gas generation repository pressure, brine saturation and brine and gas outflow. Of the variables under study, repository pressure and brine flow from the repository to the Culebra Dolomite are potentially the most important in PA for the WIPP. Subsequentmore » to a drilling intrusion repository pressure was dominated by borehole permeability and generally below the level (i.e., 8 MPa) that could potentially produce spallings and direct brine releases. Brine flow from the repository to the Culebra Dolomite tended to be small or nonexistent with its occurrence and size also dominated by borehole permeability.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Funk, David John

The inadvertent creation of transuranic waste carrying hazardous waste codes D001 and D002 requires the treatment of the material to eliminate the hazardous characteristics and allow its eventual shipment and disposal at the Waste Isolation Pilot Plant (WIPP). This report briefly summarizes the surrogate testing that was done in support of our understanding of this waste form.

Environmental and health impacts of February 14, 2014 radiation release from the nation's only deep geologic nuclear waste repository.

PubMed

Thakur, P; Lemons, B G; Ballard, S; Hardy, R

2015-08-01

The environmental impact of the February 14, 2014 radiation release from the nation's only deep geologic nuclear waste repository, the Waste Isolation Pilot Plant (WIPP) was assessed using monitoring data from an independent monitoring program conducted by the Carlsbad Environmental Monitoring & Research Center (CEMRC). After almost 15 years of safe and efficient operations, the WIPP had one of its waste drums rupture underground resulting in the release of moderate levels of radioactivity into the underground air. A small amount of radioactivity also escaped to the surface through the ventilation system and was detected above ground. It was the first unambiguous release from the WIPP repository. The dominant radionuclides released were americium and plutonium, in a ratio that matches the content of the breached drum. The accelerated air monitoring campaign, which began following the accident, indicates that releases were low and localized, and no radiation-related health effects among local workers or the public would be expected. The highest activity detected was 115.2 μBq/m(3) for (241)Am and 10.2 μBq/m(3) for (239+240)Pu at a sampling station located 91 m away from the underground air exhaust point and 81.4 μBq/m(3) of (241)Am and 5.8 μBq/m(3) of (239+240)Pu at a monitoring station located approximately one kilometer northwest of the WIPP facility. CEMRC's recent monitoring data show that the concentration levels of these radionuclides have returned to normal background levels and in many instances, are not even detectable, demonstrating no long-term environmental impacts of the recent radiation release event at the WIPP. This article presents an evaluation of almost one year of environmental monitoring data that informed the public that the levels of radiation that got out to the environment were very low and did not, and will not harm anyone or have any long-term environmental consequence. In terms of radiological risk at or in the vicinity of the WIPP site, the increased risk from the WIPP releases is exceedingly small, approaching zero. Copyright © 2015 Elsevier Ltd. All rights reserved.

75 FR 70584 - Criteria for the Certification and Recertification of the Waste Isolation Pilot Plant's...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-11-18

...With this document, the Environmental Protection Agency (EPA) recertifies that the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) continues to comply with the ``Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High- Level and Transuranic (TRU) Radioactive Waste.'' EPA initially certified that WIPP met applicable regulatory requirements on May 18, 1998, and the first shipment of waste was received at WIPP on March 26, 1999. The first Compliance Recertification Application (CRA) was submitted by DOE to EPA on March 26, 2004, and the Agency's first recertification decision was issued on March 29, 2006.

Integration of Thirty Years of Hydrogeological Investigations at the Waste Isolation Pilot Plant Site

NASA Astrophysics Data System (ADS)

Beauheim, R. L.; Domski, P. S.; Holt, R. M.; Powers, D. W.

2008-12-01

Hydrogeological research has been going on at the Waste Isolation Pilot Plant (WIPP), the U.S. Department of Energy's deep geologic repository for transuranic and mixed waste in southeastern New Mexico, for over thirty years. The main focus of the research has been on the Culebra Dolomite Member of the Rustler Formation, a 7-m-thick fractured unit that would be the primary groundwater transport pathway for radionuclides released from the WIPP repository by inadvertent human intrusion. Since 1977, 90 wells have been completed to the Culebra on 63 drilling pads. Hydraulic tests have been performed in all of the wells, ranging from single-well slug and pumping tests to long-term (19-121 days) pumping tests with observation wells up to 9.5 km away. These tests have shown that Culebra transmissivity (T) varies over 10 orders of magnitude. Single-well injection-withdrawal, two-well recirculating, and multiwell convergent-flow tracer tests have been performed at six locations. Fluid electrical conductivity logging has been performed to identify the most transmissive sections of the Culebra, and a colloidal borescope has been used to identify specific flowing fractures. In addition to studies focused on groundwater flow and transport, geological, sedimentological, hydrogeochemical, and geophysical investigations have also been performed. Variations in Culebra T have been related to dissolution of the underlying Salado Formation, the presence/absence of gypsum cements, the presence or absence of halite in Rustler members above and below the Culebra, and overburden thickness. Different types of porosity (fractures, vugs, interparticle, intercrystalline) have been found to be significant for both flow and transport. Culebra water chemistry shows significant spatial variation, with total dissolved solids ranging from 3,000 to 300,000 mg/L. Five distinct hydrochemical facies have been identified, ranging from high ionic strength syndepositional Na-Mg Cl brines to low ionic strength CaSO4 waters, thought to represent relatively recent recharge through gypsum karst, to brines contaminated with potash-processing effluent. Geophysical logs from an abundance of oil and gas wells around the WIPP site have been used to map facies boundaries within other Rustler members that can be related to Culebra hydrology. The results of these three decades of study have been integrated into a conceptual model for Culebra hydrology. Some of these studies have been carried out in collaboration with university researchers, and all of the data from these investigations are freely available. *Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy's National Nuclear Security Administration under contract DE-AC04- 94AL85000. This research is funded by WIPP programs administered by the Office of Environmental Management (EM) of the U.S DOE.

Resource Conservation and Recovery Act, Part B Permit Application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 6, Chapter D, Appendices D4--D13: Revision 1.0

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1991-12-31

This report (Vol. 6) for the WIPP facility contains appendices on the following information: Site characterization; general geology; ecological monitoring; and chemical compatibility of waste forms and container materials.

Determination of Uncertainties for +III and +IV Actinide Solubilities in the WIPP Geochemistry Model for the 2009 Compliance Recertification Application

NASA Astrophysics Data System (ADS)

Ismail, A. E.; Xiong, Y.; Nowak, E. J.; Brush, L. H.

2009-12-01

The Waste Isolation Pilot Plant (WIPP) is a U.S. Department of Energy (DOE) repository in southeast New Mexico for defense-related transuranic (TRU) waste. Every five years, the DOE is required to submit an application to the Environmental Protection Agency (EPA) demonstrating the WIPP’s continuing compliance with the applicable EPA regulations governing the repository. Part of this recertification effort involves a performance assessment—a probabilistic evaluation of the repository performance with respect to regulatory limits on the amount of releases from the repository to the accessible environment. One of the models used as part of the performance assessment process is a geochemistry model, which predicts solubilities of the radionuclides in the brines that may enter the repository in the different scenarios considered by the performance assessment. The dissolved actinide source term comprises actinide solubilities, which are input parameters for modeling the transport of radionuclides as a result of brine flow through and from the repository. During a performance assessment, the solubilities are modeled as the product of a “base” solubility determined from calculations based on the chemical conditions expected in the repository, and an uncertainty factor that describes the potential deviations of the model from expected behavior. We will focus here on a discussion of the uncertainties. To compute a cumulative distribution function (CDF) for the uncertainties, we compare published, experimentally measured solubility data to predictions made using the established WIPP geochemistry model. The differences between the solubilities observed for a given experiment and the calculated solubilities from the model are used to form the overall CDF, which is then sampled as part of the performance assessment. We will discuss the methodology used to update the CDF’s for the +III actinides, obtained from data for Nd, Am, and Cm, and the +IV actinides, obtained from data for Th, and present results for the calculations of the updated CDF’s. We compare the CDF’s to the distributions computed for the previous recertification, and discuss the potential impact of the changes on the geochemistry model. This research is funded by WIPP programs administered by the U.S. Department of Energy. Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy’s National Nuclear Security Administration under contract DE-AC04-94AL85000.

Anoxic Corrosion of Steel and Lead in Na - Cl ± Mg-Dominated Brines in Atmospheres Containing CO2

NASA Astrophysics Data System (ADS)

Roselle, G. T.; Johnsen, S.; Allen, C.; Roselle, R.

2009-12-01

The Waste Isolation Pilot Plant (WIPP) is a deep geologic repository developed by the U.S. Department of Energy for the disposal of transuranic radioactive waste in bedded salt (Permian Salado Fm.). In order to minimize radionuclide release from the repository it is desirable to maintain these species in their least-soluble form (i.e., low oxidation states). Post-closure conditions in the WIPP will control the speciation and solubility of radionuclides in the waste. Microbially-produced CO2 from cellulosic, plastic and rubber materials in the waste may acidify any brine present and increase the actinide solubilities. Thus, the DOE emplaces MgO in the repository to buffer fCO2 and pH within ranges favoring lower actinide solubilities. Large quantities of low-C steel and Pb present in the WIPP may also consume CO2. We present initial results from a series of multiyear experiments investigating the corrosion of steel and Pb alloys under WIPP-relevant conditions. The objective is to determine the extent to which these alloys consume CO2 via the formation of carbonates or other phases, potentially supporting MgO in CO2 sequestration. In these experiments steel and Pb coupons are immersed in brines under WIPP-relevant conditions using a continuous gas flow-through system. The experimental apparatus maintains the following conditions: pO2 < 5 ppm; temperature of 26 °C; relative humidity at 78%±10%; and a range of pCO2 values (0, 350, 1500 and 3500 ppm, balance N2). Four high-ionic-strength-brines are used: Generic Weep Brine (GWB), a Na-Mg-Cl dominated brine associated with the Salado Fm.; Energy Research and Development Administration WIPP Well 6 (ERDA-6), a predominately Na-Cl brine; GWB with organic ligands (EDTA, acetate, citrate, and oxalate); and ERDA-6 with the same organic ligands. Steel coupons removed after 6 months show formation of several phases dependent on the pCO2. SEM analysis with EDS shows the presence of a green Fe (±Mg)-chlori-hydroxide phase at pCO2 values <1500 ppm. At higher pCO2 the dominant corrosion product is a Fe-Mg-Ca hydroxicarbonate phase. Lead coupons show no corrosion products at lower pCO2 values but significant formation of a Pb-Ca hydroxicarbonate phase at pCO2 > 350 ppm. Multiple cleaning cycles were used to remove all corrosion products from the coupons, which were then weighed to determine corrosive mass loss. These data are used to calculate average corrosion rates for each experimental condition. The data show that steel corrosion rates are a strong function of pCO2 for all brine types. ERDA-6 brines appear to be more corrosive than GWB brines. Steel corrosion rates vary from 0.08 ± 0.07 µm/yr at 0 ppm CO2 to 1.20 ± 0.25 µm/yr at 3500 ppm CO2. Corrosion rates for Pb coupons show no consistent trend as a function of pCO2 or brine type. Lead corrosion rates range from 0.18 ± 0.22 to 0.95 ± 0.56 µm/yr. This research is funded by WIPP programs administered by the U.S. Department of Energy. Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy’s National Nuclear Security Administration under contract DE-AC04-94AL85000.

Weatherization Innovation Pilot Program (WIPP): Technical Assistance Summary

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hollander, A.

2014-09-01

The U.S. Department of Energy (DOE) Energy Efficiency and Renewable Energy (EERE) Weatherization and Intergovernmental Programs Office (WIPO) launched the Weatherization Innovation Pilot Program (WIPP) to accelerate innovations in whole-house weatherization and advance DOE's goal of increasing the energy efficiency and health and safety of low-income residences without the utilization of additional taxpayer funding. Sixteen WIPP grantees were awarded a total of $30 million in Weatherization Assistance Program (WAP) funds in September 2010. These projects focused on: including nontraditional partners in weatherization service delivery; leveraging significant non-federal funding; and improving the effectiveness of low-income weatherization through the use of newmore » materials, technologies, behavior-change models, and processes.« less

Ongoing environmental monitoring and assessment of the long-term impacts of the February 2014 radiological release from the waste isolation pilot plant.

PubMed

Thakur, Punam; Runyon, Tim

2018-04-09

Three years ago, the Waste Isolation Pilot Plant (WIPP) experienced its first minor accident involving a radiological release. Late in the evening on February 14, 2014, a waste container in the repository underwent a chemical reaction that caused the container to overheat and breach, releasing its contents into the underground. Following a lengthy recovery process, the facility recently resumed waste disposal operations. The accident released significant levels of radioactivity into the disposal room and adjacent exhaust drifts, and although no one was present in the underground at the time of the release, a total of 22 workers tested positive for very low level of radiation, presumably from some of the radioactive material that was released above ground through a small leak in the HEPA filtration system. The dominant radionuclides released were 241 Am and 239 + 240 Pu in a ratio that matched the content of the drum from Los Alamos National Laboratory (LANL) that was eventually identified as the breached container. From the air particulate monitoring and plume modeling, it was concluded that the dose, at the nearest location accessible to the general public, from this radiation release event would have been less than 0.01 mSv (< 1 mrem/year). This level is well below the 0.1 mSv/year (10 mrem/year) regulatory limit for DOE facilities established by the US Environmental Protection Agency (EPA).While no long-term impacts to public health or the environment are expected as a result of the WIPP radiation release, the limited ventilation and residual contamination levels in the underground are still a concern and pose a major challenge for the full recovery of WIPP. This article provides an up-to-date overview of environmental monitoring results through the WIPP recovery and an estimate of the long-term impacts of the accident on the natural and human environment.

Pretest reference calculation for the 18-W/m/sup 2/ Mockup for Defense High-Level Waste (WIPP Room A in situ experiment)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Morgan, H.S.; Stone, C.M.

A pretest reference calculation for the 18-W/m/sup 2/ Mockup for Defense High-Level Waste (DHLW) or Room A experiment is presented in this report. The mockup is one of several large scale in situ experiments currently under construction near Carlsbad, New Mexico, at the site of the Waste Isolation Pilot Plant (WIPP). The 18-W/m/sup 2/ test is an in situ experiment developed to simulate closely the Reference Repository Conditions (RRC) for DHLW in salt. The test consists of three long, parallel rooms (A1, A2, A3) which are heated by canister heaters placed in the floor of each room. These heaters producemore » thermal loading which simulates an areal heat output of 18-W/m/sup 2/ for Room A2, which is the focus of the experiment. This load will be supplied for a period of three years. Rooms A1, A2, and A3 are heavily instrumented for monitoring both temperature increases due to the thermal loading and deformations due to creep of the salt. Data from the experiment are not available at the present time, but the measurements for Room A2 will eventually be compared to the results for Room A2 presented here to assess and improve thermal and mechanical modeling capabilities for the WIPP. The thermal/structural model used here represents the state-of-the-art at the present time. A large number of plots are included since an appropriate result is presented for every Room A2 gauge location. 55 refs., 70 figs., 4 tabs.« less

EPA's Response to the February 2014 Release of Radioactive Material from the Waste Isolation Pilot Plant (WIPP): EPA's WIPP Air Sampling Data from April 2014

EPA Pesticide Factsheets

In April 2014, U.S. Environmental Protection Agency (EPA) environmental monitoring and assessment team members reviewed DOE's air sampling plan, visited DOE's air samplers and placed air samplers onsite near existing DOE samplers to corroborate results.

Criteria for the Certification and Recertification of the Waste Isolation Pilot Plant's Compliance with the 40 CFR Part 191 Disposal Regulations (40 CFR Part 194)

EPA Pesticide Factsheets

EPA is responsible for certifying that DOE’s Waste Isolation Pilot Plant (WIPP) remains in compliance with environmental standards for the disposal of transuranic waste. 40 CFR Part 194 specifies criteria for certification or recertification of WIPP.

MARC calculations for the second WIPP structural benchmark problem

DOE Office of Scientific and Technical Information (OSTI.GOV)

Morgan, H.S.

1981-05-01

This report describes calculations made with the MARC structural finite element code for the second WIPP structural benchmark problem. Specific aspects of problem implementation such as element choice, slip line modeling, creep law implementation, and thermal-mechanical coupling are discussed in detail. Also included are the computational results specified in the benchmark problem formulation.

78 FR 72612 - Criteria for the Certification and Recertification of the Waste Isolation Pilot Plant's...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-12-03

... WIPP PA process culminates in a series of computer simulations that model the physical attributes of... and Processes LWA Land Withdrawal Act MSHA Mine Safety and Health Administration NMED New Mexico... Agency's technical review process was to determine whether, with the new design, the WIPP adequately...

Actinide Solubility and Speciation in the WIPP [PowerPoint

DOE Office of Scientific and Technical Information (OSTI.GOV)

Reed, Donald T.

2015-11-02

The presentation begins with the role and need for nuclear repositories (overall concept, international updates (Sweden, Finland, France, China), US approach and current status), then moves on to the WIPP TRU repository concept (design, current status--safety incidents of February 5 and 14, 2014, path forward), and finally considers the WIPP safety case: dissolved actinide concentrations (overall approach, oxidation state distribution and redox control, solubility of actinides, colloidal contribution and microbial effects). The following conclusions are set forth: (1) International programs are moving forward, but at a very slow and somewhat sporadic pace. (2) In the United States, the Salt repositorymore » concept, from the perspective of the long-term safety case, remains a viable option for nuclear waste management despite the current operational issues/concerns. (3) Current model/PA prediction (WIPP example) are built on redundant conservatisms. These conservatisms are being addressed in the ongoing and future research to fill existing data gaps--redox control of plutonium by Fe(0, II), thorium (analog) solubility studies in simulated brine, contribution of intrinsic and biocolloids to the mobile concentration, and clarification of microbial ecology and effects.« less

Numerical Modeling of ROM Panel Closures at WIPP

NASA Astrophysics Data System (ADS)

Herrick, C. G.

2016-12-01

The Waste Isolation Pilot Plant (WIPP) in New Mexico is a U.S. DOE geologic repository for permanent disposal of defense-related transuranic (TRU) waste. Waste is emplaced in panels excavated in a bedded salt formation (Salado Fm.) at 655 m bgs. In 2014 the U.S. EPA approved the new Run-of-Mine Panel Closure System (ROMPCS) for WIPP. The closure system consists of 100 feet of run-of-mine (ROM) salt sandwiched between two barriers. Nuclear Waste Partnership LLC (the M&O contractor for WIPP) initiated construction of the ROMPCS. The design calls for three horizontal ROM salt layers at different compaction levels ranging from 70-85% intact salt density. Due to panel drift size constraints and equipment availability the design was modified. Three prototype panel closures were constructed: two having two layers of compacted ROM salt (one closure had 1% water added) and a third consisting of simply ROM salt with no layering or added water. Sampling of the prototype ROMPCS layers was conducted to determine the following ROM salt parameters: thickness, moisture content, emplaced density, and grain-size distribution. Previous modeling efforts were performed without knowledge of these ROM salt parameters. This modeling effort incorporates them. The program-accepted multimechanism deformation model is used to model intact salt room creep closure. An advanced crushed salt model is used to model the ROM salt. Comparison of the two models' results with the prototypes' behavior is given. Our goal is to develop a realistic, reliable model that can be used for ROM salt applications at WIPP. Sandia National Laboratories is a multi-program laboratory operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U. S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. This research is funded by WIPP programs administered by the Office of Environmental Management (EM) of the U.S Department of Energy SAND2016-7259A

The magnitude and relevance of the February 2014 radiation release from the Waste Isolation Pilot Plant repository in New Mexico, USA.

PubMed

Thakur, P; Lemons, B G; White, C R

2016-09-15

After almost fifteen years of successful waste disposal operations, the first unambiguous airborne radiation release from the Waste Isolation Pilot Plant (WIPP) was detected beyond the site boundary on February 14, 2014. It was the first accident of its kind in the 15-year operating history of the WIPP. The accident released moderate levels of radioactivity into the underground air. A small but measurable amount of radioactivity also escaped to the surface through the ventilation system and was detected above ground. The dominant radionuclides released were americium and plutonium, in a ratio consistent with the known content of a breached drum. The radiation release was caused by a runaway chemical reaction inside a transuranic (TRU) waste drum which experienced a seal and lid failure, spewing radioactive materials into the repository. According to source-term estimation, approximately 2 to 10Ci of radioactivity was released from the breached drum into the underground, and an undetermined fraction of that source term became airborne, setting off an alarm and triggering the closure of seals designed to force exhausting air through a system of filters including high-efficiency-particulate-air (HEPA) filters. Air monitoring across the WIPP site intensified following the first reports of radiation detection underground to determine the extent of impact to WIPP personnel, the public, and the environment, if any. This article attempts to compile and interpret analytical data collected by an independent monitoring program conducted by the Carlsbad Environmental Monitoring & Research Center (CEMRC) and by a compliance-monitoring program conducted by the WIPP's management and operating contractor, the Nuclear Waste Partnership (NWP), LLC., in response to the accident. Both the independent and the WIPP monitoring efforts concluded that the levels detected were very low and localized, and no radiation-related health effects among local workers or the public would be expected. Published by Elsevier B.V.

Adequacy of a Small Quantity Site RH-TRU Waste Program in Meeting Proposed WIPP Characterization Objectives

DOE Office of Scientific and Technical Information (OSTI.GOV)

Biedscheid, J.; Stahl, S.; Devarakonda, M.

2002-02-26

The first remote-handled transuranic (RH-TRU) waste is expected to be permanently disposed of at the Waste Isolation Pilot Plant (WIPP) during Fiscal Year (FY) 2003. The first RH-TRU waste shipments are scheduled from the Battelle Columbus Laboratories (BCL) to WIPP in order to facilitate compliance with BCL Decommissioning Project (BCLDP) milestones. Milestones requiring RH-TRU waste containerization and removal from the site by 2004 in order to meet a 2006 site closure goal, established by Congress in the Defense Facilities Closure Projects account, necessitated the establishment and implementation of a site-specific program to direct the packaging of BCLDP RH-TRU waste priormore » to the finalization of WIPP RH-TRU waste characterization requirements. The program was designed to collect waste data, including audio and videotape records of waste packaging, such that upon completion of waste packaging, comprehensive data records exist from which compliance with final WIPP RH-TRU waste characterization requirements can be demonstrated. With the BCLDP data records generated to date and the development by the U.S. Department of Energy (DOE)-Carlsbad Field Office (CBFO) of preliminary documents proposing the WIPP RH-TRU waste characterization program, it is possible to evaluate the adequacy of the BCLDP program with respect to meeting proposed characterization objectives. The BCLDP characterization program uses primarily acceptable knowledge (AK) and visual examination (VE) during waste packaging to characterize RH-TRU waste. These methods are used to estimate physical waste parameters, including weight percentages of metals, cellulosics, plastics, and rubber in the waste, and to determine the absence of prohibited items, including free liquids. AK combined with computer modeling is used to estimate radiological waste parameters, including total activity on a waste container basis, for the majority of BCLDP RH-TRU waste. AK combined with direct analysis is used to characterize radiological parameters for the small populations of the RH-TRU waste generated by the BCLDP. All characterization based on AK is verified. Per its design for comprehensive waste data collection, the BCLDP characterization program using AK and waste packaging procedures, including VE during packaging, meets the proposed WIPP RH-TRU waste characterization objectives. The conservative program design implemented generates certification data that will be adequate to meet any additional program requirements that may be imposed by the CBFO.« less

RH-TRU Waste Inventory Characterization by AK and Proposed WIPP RH-TRU Waste Characterization Objectives

DOE Office of Scientific and Technical Information (OSTI.GOV)

Most, W. A.; Kehrman, R.; Gist, C.

2002-02-26

The U.S. Department of Energy (DOE)-Carlsbad Field Office (CBFO) has developed draft documentation to present the proposed Waste Isolation Pilot Plant (WIPP) remote-handled (RH-) transuranic (TRU) waste characterization program to its regulators, the U.S. Environmental Protection Agency and the New Mexico Environment Department. Compliance with Title 40, Code of Federal Regulations, Parts 191 and 194; the WIPP Land Withdrawal Act (PL 102-579); and the WIPP Hazardous Waste Facility Permit, as well as the Certificates of Compliance for the 72-B and 10-160B Casks, requires that specific waste parameter limits be imposed on DOE sites disposing of TRU waste at WIPP. Themore » DOE-CBFO must control the sites' compliance with the limits by specifying allowable characterization methods. As with the established WIPP contact handled TRU waste characterization program, the DOE-CBFO has proposed a Remote-Handled TRU Waste Acceptance Criteria (RH-WAC) document consolidating the requirements from various regulatory drivers and proposed allowable characterization methods. These criteria are consistent with the recommendation of a recent National Academy Sciences/National Research Council to develop an RH-TRU waste characterization approach that removes current self imposed requirements that lack a legal or safety basis. As proposed in the draft RH-WAC and other preliminary documents, the DOE-CBFO RH-TRU waste characterization program proposes the use of acceptable knowledge (AK) as the primary method for obtaining required characterization information. The use of AK involves applying knowledge of the waste in light of the materials or processes used to generate the waste. Documentation, records, or processes providing information about various attributes of a waste stream, such as chemical, physical, and radiological properties, may be used as AK and may be applied to individual waste containers either independently or in conjunction with radiography, visual examination, assay, and other sampling and analytical data. RH-TRU waste cannot be shipped to WIPP on the basis of AK alone if documentation demonstrating that all of the prescribed limits in the RH-WAC are met is not available, discrepancies exist among AK source documents describing the same waste stream and the most conservative assumptions regarding those documents indicates that a limit will not be met, or all required data are not available for a given waste stream.« less

Krypton-81 in groundwater of the Culebra Dolomite near the Waste Isolation Pilot Plant, New Mexico

NASA Astrophysics Data System (ADS)

Sturchio, Neil C.; Kuhlman, Kristopher L.; Yokochi, Reika; Probst, Peter C.; Jiang, Wei; Lu, Zheng-Tian; Mueller, Peter; Yang, Guo-Min

2014-05-01

The Waste Isolation Pilot Plant (WIPP) in New Mexico is the first geologic repository for disposal of transuranic nuclear waste from defense-related programs of the US Department of Energy. It is constructed within halite beds of the Permian-age Salado Formation. The Culebra Dolomite, confined within Rustler Formation evaporites overlying the Salado Formation, is a potential pathway for radionuclide transport from the repository to the accessible environment in the human-disturbed repository scenario. Although extensive subsurface characterization and numerical flow modeling of groundwater has been done in the vicinity of the WIPP, few studies have used natural isotopic tracers to validate the flow models and to better understand solute transport at this site. The advent of Atom-Trap Trace Analysis (ATTA) has enabled routine measurement of cosmogenic 81Kr (half-life 229,000 yr), a near-ideal tracer for long-term groundwater transport. We measured 81Kr in saline groundwater sampled from two Culebra Dolomite monitoring wells near the WIPP site, and compared 81Kr model ages with reverse particle-tracking results of well-calibrated flow models. The 81Kr model ages are ~ 130,000 and ~ 330,000 yr for high-transmissivity and low-transmissivity portions of the formation, respectively. Compared with flow model results which indicate a relatively young mean hydraulic age (~ 32,000 yr), the 81Kr model ages imply substantial physical attenuation of conservative solutes in the Culebra Dolomite and provide limits on the effective diffusivity of contaminants into the confining aquitards.

Command and Control. Radiological Transportation Emergencies Course. Revision Three.

ERIC Educational Resources Information Center

Westinghouse Electric Corp., Carlsbad, NM.

This 12-section course is designed to explain the responsibilities of an incident commander at the scene of a Waste Isolation Pilot Plant (WIPP) transportation incident. It was created for the U.S. Department of Energy WIPP located near Carlsbad, New Mexico, which receives radioactive shipments. The course has two purposes: (1) to provide first…

40 CFR 194.8 - Approval process for waste shipment from waste generator sites for disposal at the WIPP.

Code of Federal Regulations, 2010 CFR

2010-07-01

... waste generator site will be conveyed in a letter from the Administrator's authorized representative to... transmittal to the WIPP Waste Information System database of waste characterization data, in accordance with... will be conveyed in a letter from the Administrator's authorized representative to DOE. EPA will not...

40 CFR 194.8 - Approval process for waste shipment from waste generator sites for disposal at the WIPP.

Code of Federal Regulations, 2011 CFR

2011-07-01

... waste generator site will be conveyed in a letter from the Administrator's authorized representative to... transmittal to the WIPP Waste Information System database of waste characterization data, in accordance with... will be conveyed in a letter from the Administrator's authorized representative to DOE. EPA will not...

40 CFR 194.8 - Approval process for waste shipment from waste generator sites for disposal at the WIPP.

Code of Federal Regulations, 2012 CFR

2012-07-01

... waste generator site will be conveyed in a letter from the Administrator's authorized representative to... transmittal to the WIPP Waste Information System database of waste characterization data, in accordance with... will be conveyed in a letter from the Administrator's authorized representative to DOE. EPA will not...

40 CFR 194.8 - Approval process for waste shipment from waste generator sites for disposal at the WIPP.

Code of Federal Regulations, 2013 CFR

2013-07-01

... waste generator site will be conveyed in a letter from the Administrator's authorized representative to... transmittal to the WIPP Waste Information System database of waste characterization data, in accordance with... will be conveyed in a letter from the Administrator's authorized representative to DOE. EPA will not...

Milestones for disposal of radioactive waste at the Waste Isolation Pilot Plant (WIPP) in the United States

DOE Office of Scientific and Technical Information (OSTI.GOV)

Rechard, R.P.

1998-04-01

Since its identification as a potential deep geologic repository in about 1973, the regulatory assessment process for the Waste Isolation Pilot Plant (WIPP) in New Mexico has developed over the past 25 years. National policy issues, negotiated agreements, and court settlements over the first half of the project had a strong influence on the amount and type of scientific data collected. Assessments and studies before the mid 1980s were undertaken primarily (1) to satisfy needs for environmental impact statements, (2) to develop general understanding of selected natural phenomena associated with nuclear waste disposal, or (3) to satisfy negotiated agreements withmore » the State of New Mexico. In the last third of the project, federal compliance policy and actual regulations were sketched out, but continued to evolve until 1996. During this eight-year period, four preliminary performance assessments, one compliance performance assessment, and one verification performance assessment were performed.« less

77 FR 1920 - Second Amended Notice of Intent To Modify the Scope of the Surplus Plutonium Disposition...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-01-12

... suitable for MOX fuel fabrication is disposal at the Waste Isolation Pilot Plant (WIPP) in New Mexico... Waste Processing Facility at SRS or disposal at the Waste Isolation Pilot Plant (WIPP) in New Mexico. On... are safety (criticality) limits on how much plutonium can be sent to the Defense Waste Processing...

78 FR 34380 - Biennial Determination of the Waste Isolation Pilot Plant's Compliance With Applicable Federal...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-06-07

... documentation submitted by the U.S. Department of Energy (DOE) for the Waste Isolation Pilot Plant (WIPP), the U... requirements designated in Section 9(a)(1) of the WIPP Land Withdrawal Act, as amended. The Secretary of Energy... Act; (3) the Solid Waste Disposal Act; (4) the Safe Drinking Water Act; (5) the Toxic Substances...

EVALUATION OF RISKS AND WASTE CHARACTERIZATION REQUIREMENTS FOR THE TRANSURANIC WASTE EMPLACED IN WIPP DURING 1999

DOE Office of Scientific and Technical Information (OSTI.GOV)

Channell, J.K.; Walker, B.A.

2000-05-01

Specifically this report: 1. Compares requirements of the WAP that are pertinent from a technical viewpoint with the WIPP pre-Permit waste characterization program, 2. Presents the results of a risk analysis of the currently emplaced wastes. Expected and bounding risks from routine operations and possible accidents are evaluated; and 3. Provides conclusions and recommendations.

Development of an alternate pathway for materials destined for disposition to WIPP

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ayers, Georgette Y; Mckerley, Bill; Veazey, Gerald W

2010-01-01

The Los Alamos National Laboratory currently has an inventory of process residues that may be viable candidates for disposition to the Waste Isolation Pilot Project (WIPP) located at Carlsbad, New Mexico. A recent 'Attractiveness Level D' exemption allows for the discard of specified intractable materials regardless of the percent plutonium. However, the limits with respect to drum loadings must be met. Cementation is a key component of the aqueous nitrate flowsheet and serves as a 'bleed-off' stream for impurities separated from the plutonium during processing operations. The main 'feed' to the cementation operations are the 'bottoms' from the evaporation process.more » In the majority of cases, the cemented bottoms contain less than the allowed amount per drum for WIPP acceptance. This project would expand the route to WIPP for items that have no defined disposition path, are difficult to process, have been through multiple passes, have no current recovery operations available to recover the plutonium and that are amenable to cementation. This initial work will provide the foundation for a full scale disposition pathway of the candidate materials. Once the pathway has been expanded and a cementation matrix developed, routine discard activities will be initiated.« less

76 FR 31611 - Biennial Determination of the Waste Isolation Pilot Plant's Compliance with Applicable Federal...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-06-01

... documentation submitted by the U.S. Department of Energy (DOE) for the Waste Isolation Pilot Plant (WIPP), the U... requirements designated in Section 9(a)(1) of the WIPP Land Withdrawal Act, as amended. The Secretary of Energy...) the Clean Air Act; (3) the Solid Waste Disposal Act; (4) the Safe Drinking Water Act; (5) the Toxic...

TRU waste lead organization -- WIPP Project Office Interface Management semi-annual report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Guerrero, J.V.; Gorton, J.M.

1985-05-01

The Charter establishing the Interface Control Board and the administrative organization to manage the interface of the TRU Waste Lead Organization and the WIPP Project Office also requires preparation of a summary report describing significant interface activities.'' This report includes a discussion of Interface Working Group (IWG) recommendations and resolutions considered and implemented'' over the reporting period October 1984 to March 1985.

Krypton-81 in groundwater of the Culebra Dolomite near the Waste Isolation Pilot Plant, New Mexico.

PubMed

Sturchio, Neil C; Kuhlman, Kristopher L; Yokochi, Reika; Probst, Peter C; Jiang, Wei; Lu, Zheng-Tian; Mueller, Peter; Yang, Guo-Min

2014-05-01

The Waste Isolation Pilot Plant (WIPP) in New Mexico is the first geologic repository for disposal of transuranic nuclear waste from defense-related programs of the US Department of Energy. It is constructed within halite beds of the Permian-age Salado Formation. The Culebra Dolomite, confined within Rustler Formation evaporites overlying the Salado Formation, is a potential pathway for radionuclide transport from the repository to the accessible environment in the human-disturbed repository scenario. Although extensive subsurface characterization and numerical flow modeling of groundwater has been done in the vicinity of the WIPP, few studies have used natural isotopic tracers to validate the flow models and to better understand solute transport at this site. The advent of Atom-Trap Trace Analysis (ATTA) has enabled routine measurement of cosmogenic (81)Kr (half-life 229,000 yr), a near-ideal tracer for long-term groundwater transport. We measured (81)Kr in saline groundwater sampled from two Culebra Dolomite monitoring wells near the WIPP site, and compared (81)Kr model ages with reverse particle-tracking results of well-calibrated flow models. The (81)Kr model ages are ~130,000 and ~330,000 yr for high-transmissivity and low-transmissivity portions of the formation, respectively. Compared with flow model results which indicate a relatively young mean hydraulic age (~32,000 yr), the (81)Kr model ages imply substantial physical attenuation of conservative solutes in the Culebra Dolomite and provide limits on the effective diffusivity of contaminants into the confining aquitards. Copyright © 2014 Elsevier B.V. All rights reserved.

Alternative disposal options for transuranic waste

DOE Office of Scientific and Technical Information (OSTI.GOV)

Loomis, G.G.

1994-12-31

Three alternative concepts are proposed for the final disposal of stored and retrieved buried transuranic waste. These proposed options answer criticisms of the existing U.S. Department of Energy strategy of directly disposing of stored transuranic waste in deep, geological salt formations at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The first option involves enhanced stabilization of stored waste by thermal treatment followed by convoy transportation and internment in the existing WIPP facility. This concept could also be extended to retrieved buried waste with proper permitting. The second option involves in-state, in situ internment using an encapsulating lensmore » around the waste. This concept applies only to previously buried transuranic waste. The third option involves sending stored and retrieved waste to the Nevada Test Site and configuring the waste around a thermonuclear device from the U.S. or Russian arsenal in a specially designed underground chamber. The thermonuclear explosion would transmute plutonium and disassociate hazardous materials while entombing the waste in a national sacrifice area.« less

Alternative Radiological Characterization of Sealed Source TRU Waste for WIPP Disposal (LAUR-05-8776)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Whitworth, J.; Pearson, M.; Feldman, A.

2006-07-01

The Offsite Source Recovery (OSR) Project at Los Alamos National Laboratory is now shipping transuranic (TRU) waste containers to the Waste Isolation Pilot Plant (WIPP) in New Mexico for disposal. Sealed source waste disposal has become possible in part because OSR personnel were able to obtain Environmental Protection Agency (EPA) and DOE-CBFO approval for an alternative radiological characterization procedure relying on acceptable knowledge (AK) and modeling, rather than on non-destructive assay (NDA) of each container. This is the first successful qualification of an 'alternate methodology' under the radiological characterization requirements of the WIPP Waste Acceptance Criteria (WAC) by any TRUmore » waste generator site. This paper describes the approach OSR uses to radiologically characterize its sealed source waste and the process by which it obtained certification of this approach. (authors)« less

Improved statistical assessment of a long-term groundwater-quality dataset with a non-parametric permutation method

NASA Astrophysics Data System (ADS)

Thomas, M. A.

2016-12-01

The Waste Isolation Pilot Plant (WIPP) is the only deep geological repository for transuranic waste in the United States. As the Science Advisor for the WIPP, Sandia National Laboratories annually evaluates site data against trigger values (TVs), metrics whose violation is indicative of conditions that may impact long-term repository performance. This study focuses on a groundwater-quality dataset used to redesign a TV for the Culebra Dolomite Member (Culebra) of the Permian-age Rustler Formation. Prior to this study, a TV violation occurred if the concentration of a major ion fell outside a range defined as the mean +/- two standard deviations. The ranges were thought to denote conditions that 95% of future values would fall within. Groundwater-quality data used in evaluating compliance, however, are rarely normally distributed. To create a more robust Culebra groundwater-quality TV, this study employed the randomization test, a non-parametric permutation method. Recent groundwater compositions considered TV violations under the original ion concentration ranges are now interpreted as false positives in light of the insignificant p-values calculated with the randomization test. This work highlights that the normality assumption can weaken as the size of a groundwater-quality dataset grows over time. Non-parametric permutation methods are an attractive option because no assumption about the statistical distribution is required and calculating all combinations of the data is an increasingly tractable problem with modern workstations. Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. This research is funded by WIPP programs administered by the Office of Environmental Management (EM) of the U.S. Department of Energy. SAND2016-7306A

TRU waste absorbent addition project at the Idaho National Engineering and Environmental Laboratory.

PubMed

Colson, R Griff; Auman, Laurence E

2003-08-01

ABSTRACT In order to meet a commitment to ship 3,100 m3 of transuranic waste to the Waste Isolation Pilot Plant (WIPP), the Idaho National Engineering and Environmental Laboratory (INEEL) developed a process to add absorbent to TRU waste drums that did not meet WIPP waste acceptance criteria. The development, implementation, and safe completion of this project contributed to the INEEL's success in meeting the commitment three months early.

New Mexicans debate nuclear waste disposal

DOE Office of Scientific and Technical Information (OSTI.GOV)

Lepkowski, W.

1979-01-01

A brief survey of the background of the Waste Isolation Plant (WIPP) at Carlsbad, New Mexico and the forces at play around WIPP is presented. DOE has plans to establish by 1988 an underground repository for nuclear wastes in the salt formations near Carlsbad. Views of New Mexicans, both pro and con, are reviewed. It is concluded that DOE will have to practice public persuasion to receive approval for the burial of wastes in New Mexico.

An overview of EPA regulation of the safe disposal of transuranic waste at the Waste Isolation Pilot Plant.

PubMed

Wolbarst, A B; Forinash, E K; Byrum, C O; Peake, R T; Marcinowski, F; Kruger, M U

2001-02-01

In March of 1999, the Waste Isolation Pilot Plant (WIPP) in southeast New Mexico, the world's first deep geological repository for radioactive materials, began receiving defense-related transuranic waste. The WIPP was designed and constructed by the U.S. Department of Energy, but critical to its opening was certification by the U.S. Environmental Protection Agency that the repository complies with the radioactive waste disposal regulations set forth as environmental radiation protection standards (40 CFR Part 191) and compliance criteria (40 CFR Part 194). This paper provides a summary of the regulatory process, including the Environmental Protection Agency's waste containment, groundwater protection, and individual dose regulations for the WIPP; the Department of Energy's performance assessment and the other parts of its compliance certification application; and the Environmental Protection Agency's review and analysis of the compliance certification application and related documentation.

Final environmental impact statement. Waste Isolation Pilot Plant

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1980-10-01

This volume contains the appendices for the Final Environmental Impact Statement for the Waste Isolation Pilot Plant (WIPP). Alternative geologic environs are considered. Salt, crystalline rock, argillaceous rock, and tuff are discussed. Studies on alternate geologic regions for the siting of WIPP are reviewed. President Carter's message to Congress on the management of radioactive wastes and the findings and recommendations of the interagency review group on nuclear waste management are included. Selection criteria for the WIPP site including geologic, hydrologic, tectonic, physicochemical compatability, and socio-economic factors are presented. A description of the waste types and the waste processing procedures aremore » given. Methods used to calculate radiation doses from radionuclide releases during operation are presented. A complete description of the Los Medanos site, including archaeological and historic aspects is included. Environmental monitoring programs and long-term safety analysis program are described. (DMC)« less

Waste Isolation Pilot Plant Salt Decontamination Testing

DOE Office of Scientific and Technical Information (OSTI.GOV)

Rick Demmer; Stephen Reese

2014-09-01

On February 14, 2014, americium and plutonium contamination was released in the Waste Isolation Pilot Plant (WIPP) salt caverns. At the request of WIPP’s operations contractor, Idaho National Laboratory (INL) personnel developed several methods of decontaminating WIPP salt, using surrogate contaminants and also americium (241Am). The effectiveness of the methods is evaluated qualitatively, and to the extent possible, quantitatively. One of the requirements of this effort was delivering initial results and recommendations within a few weeks. That requirement, in combination with the limited scope of the project, made in-depth analysis impractical in some instances. Of the methods tested (dry brushing,more » vacuum cleaning, water washing, strippable coatings, and mechanical grinding), the most practical seems to be water washing. Effectiveness is very high, and it is very easy and rapid to deploy. The amount of wastewater produced (2 L/m2) would be substantial and may not be easy to manage, but the method is the clear winner from a usability perspective. Removable surface contamination levels (smear results) from the strippable coating and water washing coupons found no residual removable contamination. Thus, whatever is left is likely adhered to (or trapped within) the salt. The other option that shows promise is the use of a fixative barrier. Bartlett Nuclear, Inc.’s Polymeric Barrier System (PBS) proved the most durable of the coatings tested. The coatings were not tested for contaminant entrapment, only for coating integrity and durability.« less

Continuous Improvement and the Safety Case for the Waste Isolation Pilot Plant Geologic Repository - 13467

DOE Office of Scientific and Technical Information (OSTI.GOV)

Van Luik, Abraham; Patterson, Russell; Nelson, Roger

2013-07-01

The Waste Isolation Pilot Plant (WIPP) is a geologic repository 2150 feet (650 m) below the surface of the Chihuahuan desert near Carlsbad, New Mexico. WIPP permanently disposes of transuranic waste from national defense programs. Every five years, the U.S. Department of Energy (DOE) submits an application to the U.S. Environmental Protection Agency (EPA) to request regulatory-compliance re-certification of the facility for another five years. Every ten years, DOE submits an application to the New Mexico Environment Department (NMED) for the renewal of its hazardous waste disposal permit. The content of the applications made by DOE to the EPA formore » re-certification, and to the NMED for permit-renewal, reflect any optimization changes made to the facility, with regulatory concurrence if warranted by the nature of the change. DOE points to such changes as evidence for its having taken seriously its 'continuous improvement' operations and management philosophy. Another opportunity for continuous improvement is to look at any delta that may exist between the re-certification and re-permitting cases for system safety and the consensus advice on the nature and content of a safety case as being developed and published by the Nuclear Energy Agency's Integration Group for the Safety Case (IGSC) expert group. DOE at WIPP, with the aid of its Science Advisor and teammate, Sandia National Laboratories, is in the process of discerning what can be done, in a reasonably paced and cost-conscious manner, to continually improve the case for repository safety that is being made to the two primary regulators on a recurring basis. This paper will discuss some aspects of that delta and potential paths forward to addressing them. (authors)« less

Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992. Volume 5, Uncertainty and sensitivity analyses of gas and brine migration for undisturbed performance

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1993-08-01

Before disposing of transuranic radioactive waste in the Waste Isolation Pilot Plant (WIPP), the United States Department of Energy (DOE) must evaluate compliance with applicable long-term regulations of the United States Environmental Protection Agency (EPA). Sandia National Laboratories is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for a final compliance evaluation. This volume of the 1992 PA contains results of uncertainty and sensitivity analyses with respect to migration of gas and brine from the undisturbed repository. Additional information about the 1992 PA is provided in other volumes. Volume 1 containsmore » an overview of WIPP PA and results of a preliminary comparison with 40 CFR 191, Subpart B. Volume 2 describes the technical basis for the performance assessment, including descriptions of the linked computational models used in the Monte Carlo analyses. Volume 3 contains the reference data base and values for input parameters used in consequence and probability modeling. Volume 4 contains uncertainty and sensitivity analyses with respect to the EPA`s Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191, Subpart B). Finally, guidance derived from the entire 1992 PA is presented in Volume 6. Results of the 1992 uncertainty and sensitivity analyses indicate that, conditional on the modeling assumptions and the assigned parameter-value distributions, the most important parameters for which uncertainty has the potential to affect gas and brine migration from the undisturbed repository are: initial liquid saturation in the waste, anhydrite permeability, biodegradation-reaction stoichiometry, gas-generation rates for both corrosion and biodegradation under inundated conditions, and the permeability of the long-term shaft seal.« less

Anthropogenic influences on groundwater in the vicinity of a long-lived radioactive waste repository: Anthropogenic influences on groundwater

DOE PAGES

Thomas, Matthew A.; Kuhlman, Kristopher L.; Ward, Anderson L.

2017-04-25

The groundwater flow system in the Culebra Dolomite Member (Culebra) of the Permian Rustler Formation is a potential radionuclide release pathway from the Waste Isolation Pilot Plant (WIPP), the only deep geological repository for transuranic waste in the United States. We did not expect that early conceptual models of the Culebra, groundwater levels would fluctuate markedly, except in response to long-term climatic changes, with response times on the order of hundreds to thousands of years. Recent groundwater pressures measured in monitoring wells record more than 25 m of drawdown. The fluctuations are attributed to pumping activities at a privately-owned wellmore » that may be associated with the demand of the Permian Basin hydrocarbon industry for water. Furthermore, the unprecedented magnitude of drawdown provides an opportunity to quantitatively assess the influence of unplanned anthropogenic forcings near the WIPP. Spatially variable realizations of Culebra saturated hydraulic conductivity and storativity were used to develop groundwater flow models to estimate a pumping rate for the private well and investigate its effect on advective transport. Simulated drawdown shows reasonable agreement with observations (average Model Efficiency coefficient = 0.7). Steepened hydraulic gradients associated with the pumping reduce estimates of conservative particle travel times across the domain by one-half and shift the intersection of the average particle track with the compliance boundary by more than two kilometers. Finally, the value of the transient simulations conducted for this study lie in their ability to (i) improve understanding of the Culebra groundwater flow system and (ii) challenge the notion of time-invariant land use in the vicinity of the WIPP.« less

Anthropogenic influences on groundwater in the vicinity of a long-lived radioactive waste repository: Anthropogenic influences on groundwater

DOE Office of Scientific and Technical Information (OSTI.GOV)

Thomas, Matthew A.; Kuhlman, Kristopher L.; Ward, Anderson L.

The groundwater flow system in the Culebra Dolomite Member (Culebra) of the Permian Rustler Formation is a potential radionuclide release pathway from the Waste Isolation Pilot Plant (WIPP), the only deep geological repository for transuranic waste in the United States. We did not expect that early conceptual models of the Culebra, groundwater levels would fluctuate markedly, except in response to long-term climatic changes, with response times on the order of hundreds to thousands of years. Recent groundwater pressures measured in monitoring wells record more than 25 m of drawdown. The fluctuations are attributed to pumping activities at a privately-owned wellmore » that may be associated with the demand of the Permian Basin hydrocarbon industry for water. Furthermore, the unprecedented magnitude of drawdown provides an opportunity to quantitatively assess the influence of unplanned anthropogenic forcings near the WIPP. Spatially variable realizations of Culebra saturated hydraulic conductivity and storativity were used to develop groundwater flow models to estimate a pumping rate for the private well and investigate its effect on advective transport. Simulated drawdown shows reasonable agreement with observations (average Model Efficiency coefficient = 0.7). Steepened hydraulic gradients associated with the pumping reduce estimates of conservative particle travel times across the domain by one-half and shift the intersection of the average particle track with the compliance boundary by more than two kilometers. Finally, the value of the transient simulations conducted for this study lie in their ability to (i) improve understanding of the Culebra groundwater flow system and (ii) challenge the notion of time-invariant land use in the vicinity of the WIPP.« less

U.S. Department of Energy Implementation of Chemical Evaluation Requirements for Transuranic Waste Disposal at the Waste Isolation Pilot Plant

DOE Office of Scientific and Technical Information (OSTI.GOV)

Moon, Alison; Barkley, Michelle; Poppiti, James

This report summarizes new controls designed to ensure that transuranic waste disposed at the Waste Isolation Pilot Plant (WIPP) does not contain incompatible chemicals. These new controls include a Chemical Compatibility Evaluation, an evaluation of oxidizing chemicals, and a waste container assessment to ensure that waste is safe for disposal. These controls are included in the Chapter 18 of the Documented Safety Analysis for WIPP (1).

Extent of the Disturbed Rock Zone Around a WIPP Disposal Room

NASA Astrophysics Data System (ADS)

Herrick, C. G.; Park, B. Y.; Holcomb, D. J.

2008-12-01

The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico, is operated by the U.S. Department of Energy (DOE) as the underground disposal facility for transuranic (TRU) nuclear waste. It is located in a bedded salt formation at a depth of about 650 m. Salt at this depth behaves as a viscous material having an initially lithostatic state of stress. Mining of an opening disturbs the static equilibrium to a degree where fracturing of the rock surrounding a room occurs, changing its mechanical and hydrologic properties. This disturbed rock zone (DRZ) is an important geomechanical feature included in the performance assessment process models used to predict future repository conditions as a part of certification by the EPA as meeting regulatory compliance. Based on ongoing scientific investigations and evaluation of published data since the original certification in 1998, our understanding of the DRZ has continued to progress. Three deformation processes are activated as deviatoric stresses are induced upon excavation of a room in a salt formation: (1) elastic response, (2) inelastic viscoplastic flow, and (3) inelastic- damage induced flow. Damage, the least understood of these processes, is manifested by the time- dependent initiation, growth, coalescence, and healing of microfractures with a deviatoric stress state. Since the ability to model the spatial and temporal changes in salt damage is not available at this time, various means to measure it have been attempted. At the WIPP, for this study, we used sonic velocity measurements obtained over a 12 year period as the principal field method to describe the extent of the DRZ. Predictions of the DRZ extent based on these experimental results are substantiated by permeability measurements and microfracture density analysis from other places in the repository. Extensive laboratory salt creep data demonstrate that damage can be assessed in terms of volumetric strain and principal stresses. Stress states that cause dilatant damage can be defined in terms of the ratio of stress invariants, which allow reasonable models of DRZ evolution and devolution. The change of DRZ extent with time is calculated based on a dilatant damage potential criterion: D = (C · I1) / √J2 where D is the damage potential, I1 is the first invariant of the stress tensor, and J2 is the second invariant of the deviatoric stress tensor. When D < 1, damage is predicted. The proportionality constant C in the damage criterion is determined by comparing the numerical analysis results with the sonic velocity field data obtained in the Room Q access drift of WIPP. The most extensive DRZ exists during early times, within the first ten years after a room is mined. As the creeping salt tries to fill the excavation, back stresses from the waste and gas pressure within the repository resist its deformation and damage to the salt decreases. The maximum extents of the DRZ calculated below and above a room reach approximately 2.25 m and 4.75 m, respectively. The maximum lateral DRZ extent in the side of the room is estimated to be roughly 2 m. Sandia is a multi program laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy's National Nuclear Security Administration under Contract DE-AC04-94AL85000. This research is funded by WIPP programs administered by the Office of Environmental Management (EM) of the U.S. Department of Energy.

PROBABILISTIC SAFETY ASSESSMENT OF OPERATIONAL ACCIDENTS AT THE WASTE ISOLATION PILOT PLANT

DOE Office of Scientific and Technical Information (OSTI.GOV)

Rucker, D.F.

2000-09-01

This report presents a probabilistic safety assessment of radioactive doses as consequences from accident scenarios to complement the deterministic assessment presented in the Waste Isolation Pilot Plant (WIPP) Safety Analysis Report (SAR). The International Council of Radiation Protection (ICRP) recommends both assessments be conducted to ensure that ''an adequate level of safety has been achieved and that no major contributors to risk are overlooked'' (ICRP 1993). To that end, the probabilistic assessment for the WIPP accident scenarios addresses the wide range of assumptions, e.g. the range of values representing the radioactive source of an accident, that could possibly have beenmore » overlooked by the SAR. Routine releases of radionuclides from the WIPP repository to the environment during the waste emplacement operations are expected to be essentially zero. In contrast, potential accidental releases from postulated accident scenarios during waste handling and emplacement could be substantial, which necessitates the need for radiological air monitoring and confinement barriers (DOE 1999). The WIPP Safety Analysis Report (SAR) calculated doses from accidental releases to the on-site (at 100 m from the source) and off-site (at the Exclusive Use Boundary and Site Boundary) public by a deterministic approach. This approach, as demonstrated in the SAR, uses single-point values of key parameters to assess the 50-year, whole-body committed effective dose equivalent (CEDE). The basic assumptions used in the SAR to formulate the CEDE are retained for this report's probabilistic assessment. However, for the probabilistic assessment, single-point parameter values were replaced with probability density functions (PDF) and were sampled over an expected range. Monte Carlo simulations were run, in which 10,000 iterations were performed by randomly selecting one value for each parameter and calculating the dose. Statistical information was then derived from the 10,000 iteration batch, which included 5%, 50%, and 95% dose likelihood, and the sensitivity of each assumption to the calculated doses. As one would intuitively expect, the doses from the probabilistic assessment for most scenarios were found to be much less than the deterministic assessment. The lower dose of the probabilistic assessment can be attributed to a ''smearing'' of values from the high and low end of the PDF spectrum of the various input parameters. The analysis also found a potential weakness in the deterministic analysis used in the SAR, a detail on drum loading was not taken into consideration. Waste emplacement operations thus far have handled drums from each shipment as a single unit, i.e. drums from each shipment are kept together. Shipments typically come from a single waste stream, and therefore the curie loading of each drum can be considered nearly identical to that of its neighbor. Calculations show that if there are large numbers of drums used in the accident scenario assessment, e.g. 28 drums in the waste hoist failure scenario (CH5), then the probabilistic dose assessment calculations will diverge from the deterministically determined doses. As it is currently calculated, the deterministic dose assessment assumes one drum loaded to the maximum allowable (80 PE-Ci), and the remaining are 10% of the maximum. The effective average of drum curie content is therefore less in the deterministic assessment than the probabilistic assessment for a large number of drums. EEG recommends that the WIPP SAR calculations be revisited and updated to include a probabilistic safety assessment.« less

Interpretation of data obtained from non-destructive and destructive post-test analyses of an intact-core column of culebra dolomite

DOE Office of Scientific and Technical Information (OSTI.GOV)

Lucero, Daniel L.; Perkins, W. George

The U.S. Department of Energy (DOE) has been developing a nuclear waste disposal facility, the Waste Isolation Pilot Plant (WIPP), located approximately 42 km east of Carlsbad, New Mexico. The WIPP is designed to demonstrate the safe disposal of transuranic wastes produced by the defense nuclear-weapons program. Pefiormance assessment analyses (U.S. DOE, 1996) indicate that human intrusion by inadvertent and intermittent drilling for resources provide the only credible mechanisms for significant releases of radionuclides horn the disposal system. These releases may occur by five mechanisms: (1) cuttings, (2) cavings, (3) spallings, (4) direct brine releases, and (5) long- term brinemore » releases. The first four mechanisms could result in immediate release of contaminant to the accessible environment. For the last mechanisq migration pathways through the permeable layers of rock above the Salado are important, and major emphasis is placed on the Culebra Member of the Rustler Formation because this is the most transmissive geologic layer in the disposal system. For reasons of initial quantity, half-life, and specific radioactivity, certain isotopes of T~ U, Am, and Pu would dominate calculated releases from the WIPP. In order to help quantifi parameters for the calculated releases, radionuclide transport experiments have been carried out using five intact-core columns obtained from the Culebra dolomite member of the Rustler Formation within the Waste Isolation Pilot Pknt (WIPP) site in southeastern New Mexico. This report deals primarily with results of analyses for 241Pu and 241Am distributions developed during transport experiments in one of these cores. All intact-core column transport experiments were done using Culebra-simukmt brine relevant to the core recovery location (the WIPP air-intake shaft - AK). Hydraulic characteristics (i.e., apparent porosity and apparent dispersion coefficient) for intact-core columns were obtained via experiments using conservative tracer `Na. Elution experiments carried out over periods of a few days with tracers `2U and `?Np indicated that these tracers were weakly retarded as indicated by delayed elution of these species. Elution experiments with tracers 24% and 24*Arn were performed, but no elution of either species was observed in any flow experiment to date, including experiments of many months' duration. In order to quanti~ retardation of the non-eluted species 24*Pu and 241Arn afler a period of brine flow, non-destructive and destructive analyses of an intact-core column were carried out to determine distribution of these actinides in the rock. Analytical results indicate that the majority of the 241Am is present very near the top (injection) surface of the core (possibly as a precipitate), and that the majority of the 241Pu is dispersed with a very high apparent retardation value. The 24]Pu distribution is interpreted using a single-porosity advection-dispersion model, and an approximate retardation value is reported for this actinide. The specific radionuclide isotopes used in these experiments were chosen to facilitate analysis. Even though these isotopes are not necessarily the same as those that are most important to WIPP performance, they are isotopes of the same elements, and their chemical and transport properties are therefore identical to those of isotopes in the inventory.« less

Predictions of Actinide Solubilities under Near-Field Conditions Expected in the WIPP

NASA Astrophysics Data System (ADS)

Brush, L. H.; Xiong, Y.

2009-12-01

The Waste Isolation Pilot Plant (WIPP) is a U.S. Department of Energy (DOE) repository in southeast New Mexico for defense-related transuranic (TRU) waste. The repository, which opened in March 1999, is located at a subsurface depth of 655 m (2150 ft) in the Salado Fm., a Permian bedded-salt formation. The repository will eventually contain the equivalent of 844,000 208 L (55 gal) drums of TRU waste. After filling the rooms and access drifts and installing panel closures, creep closure of the salt will crush the steel waste containers in most cases and encapsulate the waste. The WIPP actinide source term model used for long-term performance assessment (PA) of the repository comprises dissolved and suspended submodels (solubilities and colloids). This presentation will describe the solubilities. From the standpoint of long-term PA, the order of importance of the radioelements in the TRU waste to be emplaced in the WIPP is Pu ~ Am >> U > Th >> Np ~ Cm and fission products. The DOE has included all of these actinides, but not fission products, in the WIPP Actinide Source Term Program (ASTP). Anoxic corrosion of Fe- and Al-base metals and microbial consumption of cellulosic, plastic, and rubber materials will produce gas and create strongly reducing conditions in the WIPP after closure. The use of MgO as an engineered barrier to consume microbially produced CO2 will result in low fCO2 and basic pH. Under these conditions, Th, U, Np, Pu, and Am will speciate essentially entirely as Th(IV), U(IV), Np(IV), Pu(III), and Am(III); or Th(IV), U(VI), Np(V), Pu(IV), and Am(III). The DOE has developed thermodynamic speciation-and-solubility models for +III, +IV, and +V actinides in brines. Experimental data for Nd, Am, and Cm species were used to parameterize the +III Pitzer activity-coefficient model; data for Th species were used for the +IV model; and data for Np(V) species were used for the +V model. These models include the effects of the organic ligands acetate, citrate, EDTA, and oxalate in TRU waste. The oxidation-state analogy was then used to extend the +III model to Pu(III), and the +IV model to Pu(IV), U(IV), and Np(IV). The solubility of U(VI) was estimated. For the recent WIPP Compliance Recertification Application PA Baseline Calculations, we calculated actinide solubilities with fCO2 buffered at 3.14 × 10-6 atm by the brucite-hydromagnesite carbonation reaction, with pH maintained at ~9 by the brucite dissolution-precipitation reaction, and with estimated concentrations of the organic ligands in brines from the Salado and the Castile Fm., which underlies the Salado. The calculated +III, +IV, and +V solubilities are 1.56 × 10-6, 5.64 × 10-8, and 4.07 × 10-7 M, respectively, in Salado brine; and 1.51 × 10-6, 6.98 × 10-8, and 8.75 × 10-7 M in Castile brine. The U(VI) solubility estimated for both brines is 1 × 10-3 M. This research is funded by WIPP programs administered by the U.S. Department of Energy. Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy’s National Nuclear Security Administration under contract DE-AC04-94AL85000.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Carlsbad Field Office

The Performance Demonstration Program (PDP) for headspace gases distributes blind audit samples in a gas matrix for analysis of volatile organic compounds (VOCs). Participating measurement facilities (i.e., fixed laboratories, mobile analysis systems, and on-line analytical systems) are located across the United States. Each sample distribution is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed for transuranic (TRU) waste characterization. The primary documents governing the conduct of the PDP are the Quality Assurance Program Document (QAPD) (DOE/CBFO-94-1012) and the Waste Isolation Pilot Plant (WIPP) Waste Analysis Plan (WAP) contained in the Hazardousmore » Waste Facility Permit (NM4890139088-TSDF) issued by the New Mexico Environment Department (NMED). The WAP requires participation in the PDP; the PDP must comply with the QAPD and the WAP. This plan implements the general requirements of the QAPD and the applicable requirements of the WAP for the Headspace Gas (HSG) PDP. Participating measurement facilities analyze blind audit samples of simulated TRU waste package headspace gases according to the criteria set by this PDP Plan. Blind audit samples (hereafter referred to as PDP samples) are used as an independent means to assess each measurement facility’s compliance with the WAP quality assurance objectives (QAOs). To the extent possible, the concentrations of VOC analytes in the PDP samples encompass the range of concentrations anticipated in actual TRU waste package headspace gas samples. Analyses of headspace gases are required by the WIPP to demonstrate compliance with regulatory requirements. These analyses must be performed by measurement facilities that have demonstrated acceptable performance in this PDP. These analyses are referred to as WIPP analyses and the TRU waste package headspace gas samples on which they are performed are referred to as WIPP samples in this document. Participating measurement facilities must analyze PDP samples using the same procedures used for routine waste characterization analyses of WIPP samples.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Carlsbad Field Office

The Performance Demonstration Program (PDP) for headspace gases distributes sample gases of volatile organic compounds (VOCs) for analysis. Participating measurement facilities (i.e., fixed laboratories, mobile analysis systems, and on-line analytical systems) are located across the United States. Each sample distribution is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed for transuranic (TRU) waste characterization. The primary documents governing the conduct of the PDP are the Quality Assurance Program Document (QAPD) (DOE/CBFO-94-1012) and the Waste Isolation Pilot Plant (WIPP) Waste Analysis Plan (WAP) contained in the Hazardous Waste Facility Permit (NM4890139088-TSDF) issuedmore » by the New Mexico Environment Department (NMED). The WAP requires participation in the PDP; the PDP must comply with the QAPD and the WAP. This plan implements the general requirements of the QAPD and the applicable requirements of the WAP for the Headspace Gas (HSG) PDP. Participating measurement facilities analyze blind audit samples of simulated TRU waste package headspace gases according to the criteria set by this PDP Plan. Blind audit samples (hereafter referred to as PDP samples) are used as an independent means to assess each measurement facility’s compliance with the WAP quality assurance objectives (QAOs). To the extent possible, the concentrations of VOC analytes in the PDP samples encompass the range of concentrations anticipated in actual TRU waste package headspace gas samples. Analyses of headspace gases are required by the WIPP to demonstrate compliance with regulatory requirements. These analyses must be performed by measurement facilities that have demonstrated acceptable performance in this PDP. These analyses are referred to as WIPP analyses and the TRU waste package headspace gas samples on which they are performed are referred to as WIPP samples in this document. Participating measurement facilities must analyze PDP samples using the same procedures used for routine waste characterization analyses of WIPP samples.« less

Compaction behavior of surrogate degraded emplaced WIPP waste.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Broome, Scott Thomas; Bronowski, David R.; Kuthakun, Souvanny James

The present study results are focused on laboratory testing of surrogate waste materials. The surrogate wastes correspond to a conservative estimate of degraded Waste Isolation Pilot Plant (WIPP) containers and TRU waste materials at the end of the 10,000 year regulatory period. Testing consists of hydrostatic, triaxial, and uniaxial strain tests performed on surrogate waste recipes that were previously developed by Hansen et al. (1997). These recipes can be divided into materials that simulate 50% and 100% degraded waste by weight. The percent degradation indicates the anticipated amount of iron corrosion, as well as the decomposition of cellulosics, plastics, andmore » rubbers (CPR). Axial, lateral, and volumetric strain and axial, lateral, and pore stress measurements were made. Two unique testing techniques were developed during the course of the experimental program. The first involves the use of dilatometry to measure sample volumetric strain under a hydrostatic condition. Bulk moduli of the samples measured using this technique were consistent with those measured using more conventional methods. The second technique involved performing triaxial tests under lateral strain control. By limiting the lateral strain to zero by controlling the applied confining pressure while loading the specimen axially in compression, one can maintain a right-circular cylindrical geometry even under large deformations. This technique is preferred over standard triaxial testing methods which result in inhomogeneous deformation or (3z(Bbarreling(3y. (BManifestations of the inhomogeneous deformation included non-uniform stress states, as well as unrealistic Poissons ratios (> 0.5) or those that vary significantly along the length of the specimen. Zero lateral strain controlled tests yield a more uniform stress state, and admissible and uniform values of Poissons ratio.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Klein, Thomas; Patterson, Russell; Camphouse, Chris

There are two primary regulatory requirements for Panel Closures at the Waste Isolation Pilot Plant (WIPP), the nation's only deep geologic repository for defense related Transuranic (TRU) and Mixed TRU waste. The Federal requirement is through 40 CFR 191 and 194, promulgated by the U.S. Environmental Protection Agency (EPA). The state requirement is regulated through the authority of the Secretary of the New Mexico Environment Department (NMED) under the New Mexico Hazardous Waste Act (HWA), New Mexico Statutes Annotated (NMSA) 1978, chap. 74-4-1 through 74-4-14, in accordance with the New Mexico Hazardous Waste Management Regulations (HWMR), 20.4.1 New Mexico Annotatedmore » Code (NMAC). The state regulations are implemented for the operational period of waste emplacement plus 30 years whereas the federal requirements are implemented from the operational period through 10,000 years. The 10,000 year federal requirement is related to the adequate representation of the panel closures in determining long-term performance of the repository. In Condition 1 of the Final Certification Rulemaking for 40 CFR Part 194, the EPA required a specific design for the panel closure system. The U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) has requested, through the Planned Change Request (PCR) process, that the EPA modify Condition 1 via its rulemaking process. The DOE has also requested, through the Permit Modification Request (PMR) process, that the NMED modify the approved panel closure system specified in Permit Attachment G1. The WIPP facility is carved out of a bedded salt formation 655 meters below the surface of southeast New Mexico. Condition 1 of the Final Certification Rulemaking specifies that the waste panels be closed using Option D which is a combination of a Salado mass concrete (SMC) monolith and an isolation/explosion block wall. The Option D design was also accepted as the panel closure of choice by the NMED. After twelve years of waste handling operations and a greater understanding of the waste and the behavior of the underground salt formation, the DOE has established a revised panel closure design. This revised design meets both the short-term NMED Permit requirements for the operational period, and also the Federal requirements for long-term repository performance. This new design is simpler, easier to construct and has less of an adverse impact on waste disposal operations than the originally approved Option D design. The Panel Closure Redesign is based on: (1) the results of in-situ constructability testing performed to determine run-of-mine salt reconsolidation parameters and how the characteristics of the bedded salt formation affect these parameters and, (2) the results of air flow analysis of the new design to determine that the limit for the migration of Volatile Organic Compounds (VOCs) will be met at the compliance point. Waste panel closures comprise a repository feature that has been represented in WIPP performance assessment (PA) since the original Compliance Certification Application of 1996. Panel closures are included in WIPP PA models principally because they are a part of the disposal system, not because they play a substantive role in inhibiting the release of radionuclides to the outside environment. The 1998 rulemaking that certified WIPP to receive transuranic waste placed conditions on the panel closure design to be implemented in the repository. The revised panel closure design, termed the Run-of-Mine (ROM) Panel Closure System (ROMPCS), is comprised of 30.48 meters of ROM salt with barriers at each end. The ROM salt is generated from ongoing mining operations at the WIPP and may be compacted and/or moistened as it is emplaced in a panel entry. The barriers consist of bulkheads, similar to those currently used in the panels as room closures. A WIPP performance assessment has been completed that incorporates the ROMPCS design into the representation of the repository, and compares repository performance to that achieved with the approved Option D design. Several key physical processes and rock mechanics principles are incorporated into the performance assessment. First, creep closure of the salt rock surrounding a panel entry results in consolidation of the ROM salt emplaced in the entry. Eventually, the ROM salt comprising the ROMPCS will approach a condition similar to intact salt. As the ROM salt reaches higher fractional densities during consolidation, back stress will be imposed on the surrounding rock mass leading to eventual healing of the disturbed rock zone above and below the panel closure. Healing of the disturbed rock zone above and below the ROMPCS reduces the porosity and permeability in those areas. Analysis of the new design demonstrates that: (1) the WIPP continues to meet regulatory compliance requirements when the ROMPCS design is implemented instead of Option D, and (2) there is no impact on the short-term effectiveness of the panel closure to limit the concentration of VOCs at the WIPP site boundary to a fraction of the health-based exposure limits (HBLs) during the operational period. (authors)« less

Consensus on Intermediate Scale Salt Field Test Design

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kuhlman, Kristopher L.; Mills, Melissa Marie; Matteo, Edward N.

This report summarizes the first stage in a collaborative effort by Sandia, Los Alamos, and Lawrence Berkeley National Laboratories to design a small-diameter borehole heater test in salt at the Waste Isolation Pilot Plant (WIPP) for the US Department of Energy Office of Nuclear Energy (DOE-NE). The intention is to complete test design during the remainder of fiscal year 2017 (FY17), and the implementation of the test will begin in FY18. This document is the result of regular meetings between the three national labs and the DOE-NE, and is intended to represent a consensus of these meetings and discussions.

Interpretation of actinide-distribution data obtained from non-destructive and destructive post-test analyses of an intact-core column of Culebra dolomite.

PubMed

Perkins, W G; Lucero, D A

2001-02-01

The US Department of Energy (DOE), with technical assistance from Sandia National Laboratories, has successfully received EPA certification and opened the Waste Isolation Pilot Plant (WIPP), a nuclear waste disposal facility located approximately 42 km east of Carlsbad, NM. Performance assessment (PA) analyses indicate that human intrusions by inadvertent, intermittent drilling for resources provide the only credible mechanisms for significant releases of radionuclides from the disposal system. For long-term brine releases, migration pathways through the permeable layers of rock above the Salado formation are important. Major emphasis is placed on the Culebra Member of the Rustler Formation because this is the most transmissive geologic layer overlying the WIPP site. In order to help quantify parameters for the calculated releases, radionuclide transport experiments have been carried out using intact-core columns obtained from the Culebra dolomite member of the Rustler Formation within the WIPP site. This paper deals primarily with results of analyses for 241Pu and 241Am distributions developed during transport experiments in one of these cores. Transport experiments were done using a synthetic brine that simulates Culebra brine at the core recovery location (the WIPP air-intake shaft (AIS)). Hydraulic characteristics (i.e., apparent porosity and apparent dispersion coefficient) for intact-core columns were obtained via experiments using the conservative tracer 22Na. Elution experiments carried out over periods of a few days with tracers 232U and 239Np indicated that these tracers were weakly retarded as indicated by delayed elution of the species. Elution experiments with tracers 241Pu and 241Am were attempted but no elution of either species has been observed to date, including experiments of many months' duration. In order to quantify retardation of the non-eluted species 241Pu and 241Am after a period of brine flow, non-destructive and destructive analyses of one intact-core column were carried out to determine distribution of these actinides in the rock. Analytical results indicate that the majority of the 241Am remained very near the injection surface of the core (possibly as a precipitate), and that the majority of the 241Pu was dispersed with a very high apparent retardation value. The 241Pu distribution is interpreted using a single-porosity advection-dispersion model, and an approximate retardation value is reported.

Comparative study of Waste Isolation Pilot Plant (WIPP) transportation alternatives

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

WIPP transportation studies in the Final Supplement Environmental Impact Statement for WIPP are the baseline for this report. In an attempt to present the most current analysis, this study incorporates the most relevant data available. The following three transportation options are evaluated for the Disposal Phase, which is assumed to be 20 years: Truck shipments, consisting of a tractor and trailer, with three TRUPACT-IIs or one RH-72B; Regular commercial train shipments consisting of up to three railcars carrying up to 18 TRUPACT-IIs or up to six RH-72Bs; Dedicated train shipments consisting of a locomotive, an idle car, railcars carrying 18more » TRUPACT-IIs or six RH-72Bs, another idle car, and a caboose or passenger car with an emergency response specialist. No other cargo is carried. This report includes: A consideration of occupational and public risks and exposures, and other environmental impacts; A consideration of emergency response capabilities; and An extimation of comparative costs.« less

An introduction to the mechanics of performance assessment using examples of calculations done for the Waste Isolation Pilot Plant between 1990 and 1992

DOE Office of Scientific and Technical Information (OSTI.GOV)

Rechard, R.P.

1995-10-01

This document provides an overview of the process used to assess the performance of the Waste Isolation Pilot Plant (WIPP), a proposed repository for transuranic wastes that is located in southeastern New Mexico. The quantitative metrics used in the performance-assessment (PA) process are those put forward in the Environmental Protection Agency`s Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive flasks (40 CFR 191). Much has been written about the individual building blocks that comprise the foundation of PA theory and practice, and that WIPP literature is well cited herein. However, the present approachmore » is to provide an accurate, well documented overview of the process, from the perspective of the mechanical steps used to perform the actual PA calculations. Specifically, the preliminary stochastic simulations that comprise the WIPP PAs of 1990, 1991. and 1992 are summarized.« less

Irradiated Beryllium Disposal Workshop, Idaho Falls, ID, May 29-30, 2002

DOE Office of Scientific and Technical Information (OSTI.GOV)

Longhurst, Glen Reed; Anderson, Gail; Mullen, Carlan K

2002-07-01

In 2001, while performing routine radioactive decay heat rate calculations for beryllium reflector blocks for the Advanced Test Reactor (ATR), it became evident that there may be sufficient concentrations of transuranic isotopes to require classification of this irradiated beryllium as transuranic waste. Measurements on samples from ATR reflector blocks and further calculations confirmed that for reflector blocks and outer shim control cylinders now in the ATR canal, transuranic activities are about five times the threshold for classification. That situation implies that there is no apparent disposal pathway for this material. The problem is not unique to the ATR. The Highmore » Flux Isotope Reactor at Oak Ridge National Laboratory, the Missouri University Research Reactor at Columbia, Missouri and other reactors abroad must also deal with this issue. A workshop was held in Idaho Falls Idaho on May 29-30, 2002 to acquaint stakeholders with these findings and consider a path forward in resolving the issues attendant to disposition of irradiated material. Among the findings from this workshop were (1) there is a real potential for the US to be dependent on foreign sources for metallic beryllium within about a decade; (2) there is a need for a national policy on beryllium utilization and disposition and for a beryllium coordinating committee to be assembled to provide guidance on that policy; (3) it appears it will be difficult to dispose of this material at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico due to issues of Defense classification, facility radioactivity inventory limits, and transportation to WIPP; (4) there is a need for a funded DOE program to seek resolution of these issues including research on processing techniques that may make this waste acceptable in an existing disposal pathway or allow for its recycle.« less

Idaho National Engineering Laboratory code assessment of the Rocky Flats transuranic waste

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1995-07-01

This report is an assessment of the content codes associated with transuranic waste shipped from the Rocky Flats Plant in Golden, Colorado, to INEL. The primary objective of this document is to characterize and describe the transuranic wastes shipped to INEL from Rocky Flats by item description code (IDC). This information will aid INEL in determining if the waste meets the waste acceptance criteria (WAC) of the Waste Isolation Pilot Plant (WIPP). The waste covered by this content code assessment was shipped from Rocky Flats between 1985 and 1989. These years coincide with the dates for information available in themore » Rocky Flats Solid Waste Information Management System (SWIMS). The majority of waste shipped during this time was certified to the existing WIPP WAC. This waste is referred to as precertified waste. Reassessment of these precertified waste containers is necessary because of changes in the WIPP WAC. To accomplish this assessment, the analytical and process knowledge available on the various IDCs used at Rocky Flats were evaluated. Rocky Flats sources for this information include employee interviews, SWIMS, Transuranic Waste Certification Program, Transuranic Waste Inspection Procedure, Backlog Waste Baseline Books, WIPP Experimental Waste Characterization Program (headspace analysis), and other related documents, procedures, and programs. Summaries are provided of: (a) certification information, (b) waste description, (c) generation source, (d) recovery method, (e) waste packaging and handling information, (f) container preparation information, (g) assay information, (h) inspection information, (i) analytical data, and (j) RCRA characterization.« less

Waste Isolation Pilot Plant Annual Site Environmental Report for 2014. Emended

DOE Office of Scientific and Technical Information (OSTI.GOV)

none,

2015-09-01

The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2014 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1B, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: Characterize site environmental management performance; Summarize environmental occurrences and responses reported during the calendar year (CY); Confirm compliance with environmental standards and requirements; Highlight significant environmental accomplishments, including progress toward the DOE environmental sustainability goals made through implementation of the WIPP Environmental Management System (EMS).

Waste Isolation Pilot Plant Materials Interface Interactions Test: Papers presented at the Commission of European Communities workshop on in situ testing of radioactive waste forms and engineered barriers

DOE Office of Scientific and Technical Information (OSTI.GOV)

Molecke, M.A.; Sorensen, N.R.; Wicks, G.G.

The three papers in this report were presented at the second international workshop to feature the Waste Isolation Pilot Plant (WIPP) Materials Interface Interactions Test (MIIT). This Workshop on In Situ Tests on Radioactive Waste Forms and Engineered Barriers was held in Corsendonk, Belgium, on October 13--16, 1992, and was sponsored by the Commission of the European Communities (CEC). The Studiecentrum voor Kernenergie/Centre D`Energie Nucleaire (SCK/CEN, Belgium), and the US Department of Energy (via Savannah River) also cosponsored this workshop. Workshop participants from Belgium, France, Germany, Sweden, and the United States gathered to discuss the status, results and overviews ofmore » the MIIT program. Nine of the twenty-five total workshop papers were presented on the status and results from the WIPP MIIT program after the five-year in situ conclusion of the program. The total number of published MIIT papers is now up to almost forty. Posttest laboratory analyses are still in progress at multiple participating laboratories. The first MIIT paper in this document, by Wicks and Molecke, provides an overview of the entire test program and focuses on the waste form samples. The second paper, by Molecke and Wicks, concentrates on technical details and repository relevant observations on the in situ conduct, sampling, and termination operations of the MIIT. The third paper, by Sorensen and Molecke, presents and summarizes the available laboratory, posttest corrosion data and results for all of the candidate waste container or overpack metal specimens included in the MIIT program.« less

Waste Isolation Pilot Plant Biennial Environmental Compliance Report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Washinton TRU Solutions LLC

This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 2000, to March 31, 2002. As required by the WIPP Land Withdrawal Act (LWA)(Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) Carlsbad Field Office's (CBFO) compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico. In the prior BECR, the CBFO andmore » the management and operating contractor (MOC)committed to discuss resolution of a Letter of Violation that had been issued by the New Mexico Environment Department (NMED) in August 1999, which was during the previous BECR reporting period. This Letter of Violation alleged noncompliance with hazardous waste aisle spacing, labeling, a nd tank requirements. At the time of publication of the prior BECR, resolution of the Letter of Violation was pending. On July 7, 2000, the NMED issued a letter noting that the aisle spacing and labeling concerns had been adequately addressed and that they were rescinding the violation alleging that the Exhaust Shaft Catch Basin failed to comply with the requirements for a hazardous waste tank. During the current reporting period, WIPP received a Notice of Violation and a compliance order alleging the violation of the New Mexico Hazardous Waste Regulations and the WIPP Hazardous Waste Facility Permit (HWFP).« less

Effects of salt loading and flow blockage on the WIPP shrouded probe

DOE Office of Scientific and Technical Information (OSTI.GOV)

Chandra, S.; Ortiz, C.A.; McFarland, A.R.

1993-08-01

The shrouded probes at the WIPP site operate in a salt aerosol environment that can cause a buildup of salt deposits on exposed surfaces of the probes that, in turn, could produce changes in the sampling performance of the probes. At Station A, three probes had been operated for a period of approximately 2 1/2 years when they were inspected with a remote television camera. There were visible deposits of unknown thickness on the probes, so WIPP removed the probes for inspection and cleanup. Measurements were made on the probes and they showed the buildups to be approximately 2.5 mmmore » thick on the most critical dimension of a shrouded probe, which is the inside diameter of the inner probe. For reference, the diameter of a clean probe is 30 mm. The sampling performance of this particular shrouded probe had been previously evaluated in a wind tunnel at Aerosol Technology Laboratory (ATL) of Texas A&M University for two free stream velocities (14 and 21 m/s) and three particle sizes (5, 10 and 15 {mu}m AED).« less

Pretest parametric calculations for the heated pillar experiment in the WIPP In-Situ Experimental Area

DOE Office of Scientific and Technical Information (OSTI.GOV)

Branstetter, L.J.

Results are presented for a pretest parametric study of several configurations and heat loads for the heated pillar experiment (Room H) in the Waste Isolation Pilot Plant (WIPP) In Situ Experimental Area. The purpose of this study is to serve as a basis for selection of a final experiment geometry and heat load. The experiment consists of a pillar of undisturbed rock salt surrounded by an excavated annular room. The pillar surface is covered by a blanket heat source which is externally insulated. A total of five thermal and ten structural calculations are described in a four to five yearmore » experimental time frame. Results are presented which include relevant temperature-time histories, deformations, rock salt stress component and effective stress profiles, and maximum stresses in anhydrite layers which are in close proximity to the room. Also included are predicted contours of a conservative post-processed measure of potential salt failure. Observed displacement histories are seen to be highly dependent on pillar and room height, but insensitive to other geometrical variations. The use of a tensile cutoff across slidelines is seen to produce more accurate predictions of anhydrite maximum stress, but to have little effect on rock salt stresses. The potential for salt failure is seen to be small in each case for the time frame of interest, and is only seen at longer times in the center of the room floor.« less

The role of acceptable knowledge in transuranic waste disposal operations - 11117

DOE Office of Scientific and Technical Information (OSTI.GOV)

Chancellor, Christopher John; Nelson, Roger

2010-11-08

The Acceptable Knowledge (AK) process plays a key role in the delineation of waste streams destined for the Waste Isolation Pilot Plant (WIPP). General Electric's Vallecitos Nuclear Center (GEVNC) provides for an ideal case study of the application of AK in a multiple steward environment. In this review we will elucidate the pivotal role Acceptable Knowledge played in segregating Department of Energy (DOE) responsibilities from a commercial facility. The Acceptable Knowledge process is a necessary component of waste characterization that determines whether or not a waste stream may be considered for disposal at the WIPP site. This process may bemore » thought of as an effort to gain a thorough understanding of the waste origin, chemical content, and physical form gleaned by the collection of documentation that concerns generator/storage site history, mission, and operations; in addition to waste stream specific information which includes the waste generation process, the waste matrix, the quantity of waste concerned, and the radiological and chemical make up of the waste. The collection and dissemination of relevant documentation is the fundamental requirement for the AK process to work. Acceptable Knowledge is the predominant process of characterization and, therefore, a crucial part of WIPP's transuranic waste characterization program. This characterization process, when conducted to the standards set forth in WIPP's operating permit, requires confirmation/verification by physical techniques such as Non-Destructive Examination (NDE), Visual Examination (VE), and Non-Destructive Assay (NDA). These physical characterization techniques may vary in their appropriateness for a given waste stream; however, nothing will allow the substitution or exclusion of AK. Beyond the normal scope of operations, AK may be considered, when appropriate, a surrogate for the physical characterization techniques in a procedure that appeals to concepts such As Low As Reasonably Achievable (ALARA) and budgetary savings. This substitution is referred to as an Acceptable Knowledge Sufficiency Determination. With a Sufficiency Determination Request, AK may supplant the need for one or all of the physical analysis methods. This powerful procedure may be used on a scale as small as a single container to that of a vast waste stream. Only under the most stringent requirements will an AK Sufficiency Determination be approved by the regulators and, to date, only six such Sufficiency Determinations have been approved. Although Acceptable Knowledge is legislated into the operational procedures of the WIPP facility there is more to it than compliance. AK is not merely one of a long list of requirements in the characterization and verification of transuranic (TRU) waste destined for the WIPP. Acceptable Knowledge goes beyond the regulatory threshold by offering a way to reduce risk, cost, time, and uncertainty on its own laurels. Therefore, AK alone can be argued superior to any other waste characterization technique.« less

Waste Generator Instructions: Key to Successful Implementation of the US DOE's 435.1 for Transuranic Waste Packaging Instructions (LA-UR-12-24155) - 13218

DOE Office of Scientific and Technical Information (OSTI.GOV)

French, David M.; Hayes, Timothy A.; Pope, Howard L.

In times of continuing fiscal constraints, a management and operation tool that is straightforward to implement, works as advertised, and virtually ensures compliant waste packaging should be carefully considered and employed wherever practicable. In the near future, the Department of Energy (DOE) will issue the first major update to DOE Order 435.1, Radioactive Waste Management. This update will contain a requirement for sites that do not have a Waste Isolation Pilot Plant (WIPP) waste certification program to use two newly developed technical standards: Contact-Handled Defense Transuranic Waste Packaging Instructions and Remote-Handled Defense Transuranic Waste Packaging Instructions. The technical standards aremore » being developed from the DOE O 435.1 Notice, Contact-Handled and Remote-Handled Transuranic Waste Packaging, approved August 2011. The packaging instructions will provide detailed information and instruction for packaging almost every conceivable type of transuranic (TRU) waste for disposal at WIPP. While providing specificity, the packaging instructions leave to each site's own discretion the actual mechanics of how those Instructions will be functionally implemented at the floor level. While the Technical Standards are designed to provide precise information for compliant packaging, the density of the information in the packaging instructions necessitates a type of Rosetta Stone that translates the requirements into concise, clear, easy to use and operationally practical recipes that are waste stream and facility specific for use by both first line management and hands-on operations personnel. The Waste Generator Instructions provide the operator with step-by-step instructions that will integrate the sites' various operational requirements (e.g., health and safety limits, radiological limits or dose limits) and result in a WIPP certifiable waste and package that can be transported to and emplaced at WIPP. These little known but widely productive Waste Generator Instructions (WGIs) have been used occasionally in the past at large sites for treatment and packaging of TRU waste. The WGIs have resulted in highly efficient waste treatment, packaging and certification for disposal of TRU waste at WIPP. For example, a single WGI at LANL, combined with an increase in gram loading, resulted in a mind boggling 6,400% increase in waste loading for {sup 238}Pu heat source waste. In fact, the WGI combined with a new Contact Handled (CH) TRU Waste Content (TRUCON) Code provided a massive increase in shippable wattage per Transuranic Package Transporter-II (TRUPACT-II) over the previously used and more restrictive TRUCON Code that have been used previously for the heat source waste. In fact, the use of the WGI process at LANL's TA-55 facility reduced non-compliant drums for WIPP certification and disposal from a 13% failure rate down to a 0.5% failure rate and is expected to further reduce the failure rate to zero drums per year. The inherent value of the WGI is that it can be implemented in a site's current procedure issuance process and it provides documented proof of what actions were taken for each waste stream packaged. The WGI protocol provides a key floor-level operational component to achieve goal alignment between actual site operations, the WIPP TRU waste packaging instructions, and DOE O 435.1. (authors)« less

Characterization of the Old Hydrofracture Facility (OHF) waste tanks located at ORNL

DOE Office of Scientific and Technical Information (OSTI.GOV)

Keller, J.M.; Giaquinto, J.M.; Meeks, A.M.

1997-04-01

The Old Hydrofracture Facility (OHF) is located in Melton Valley within Waste Area Grouping (WAG) 5 and includes five underground storage tanks (T1, T2, T3, T4, and T9) ranging from 13,000 to 25,000 gal. capacity. During the period of 1996--97 there was a major effort to re-sample and characterize the contents of these inactive waste tanks. The characterization data summarized in this report was needed to address waste processing options, examine concerns dealing with the performance assessment (PA) data for the Waste Isolation Pilot Plant (WIPP), evaluate the waste characteristics with respect to the waste acceptance criteria (WAC) for WIPPmore » and Nevada Test Site (NTS), address criticality concerns, and to provide the data needed to meet DOT requirements for transporting the waste. This report discusses the analytical characterization data collected on both the supernatant and sludge samples taken from three different locations in each of the OHF tanks. The isotopic data presented in this report supports the position that fissile isotopes of uranium ({sup 233}U and {sup 235}U) do not satisfy the denature ratios required by the administrative controls stated in the ORNL LLLW waste acceptance criteria (WAC). The fissile isotope of plutonium ({sup 239}Pu and {sup 241}Pu) are diluted with thorium far above the WAC requirements. In general, the OHF sludge was found to be hazardous (RCRA) based on total metal content and the transuranic alpha activity was well above the 100 nCi/g limit for TRU waste. The characteristics of the OHF sludge relative to the WIPP WAC limits for fissile gram equivalent, plutonium equivalent activity, and thermal power from decay heat were estimated from the data in this report and found to be far below the upper boundary for any of the remote-handled transuranic waste (RH-TRU) requirements for disposal of the waste in WIPP.« less

Innovations in the Assay of Un-Segregated Multi-Isotopic Grade TRU Waste Boxes with SuperHENC and FRAM Technology

DOE Office of Scientific and Technical Information (OSTI.GOV)

Simpson, A. P.; Barber, S.; Abdurrahman, N. M.

2006-07-01

The Super High Efficiency Neutron Coincidence Counter (SuperHENC) was originally developed by BIL Solutions Inc., Los Alamos National Laboratory (LANL) and Rocky Flats Environmental Technology Site (RFETS) for assay of transuranic (TRU) waste in Standard Waste Boxes (SWB) at Rocky Flats. This mobile system was a key component in the shipment of over 4,000 SWBs to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The system was WIPP certified in 2001 and operated at the site for four years. The success of this system, a passive neutron coincidence counter combined with high resolution gamma spectroscopy, led to themore » order of two new units, delivered to Hanford in 2004. Several new challenges were faced at Hanford: For example, the original RFETS system was calibrated for segregated waste streams such that metals, plastics, wet combustibles and dry combustibles were separated by 'Item Description Codes' prior to assay. Furthermore, the RFETS mission of handling only weapons grade plutonium, enabled the original SuperHENC to benefit from the use of known Pu isotopics. Operations at Hanford, as with most other DOE sites, generate un-segregated waste streams, with a wide diversity of Pu isotopics. Consequently, the new SuperHENCs are required to deal with new technical challenges. The neutron system's software and calibration methodology have been modified to encompass these new requirements. In addition, PC-FRAM software has been added to the gamma system, providing a robust isotopic measurement capability. Finally a new software package has been developed that integrates the neutron and gamma data to provide a final assay results and analysis report. The new system's performance has been rigorously tested and validated against WIPP quality requirements. These modifications, together with the mobile platform, make the new SuperHENC far more versatile in handling diverse waste streams and allow for rapid redeployment around the DOE complex. (authors)« less

Pretest 3D finite element analysis of the WIPP Intermediate Scale Borehole Test

DOE Office of Scientific and Technical Information (OSTI.GOV)

Arguello, J.G.

A three dimensional pretest finite element analysis of the Intermediate Scale Borehole Test has been performed. In the analysis, the 7.7 years simulation period includes the mining of Rooms C1 and C2, and the N1420 cross drift, at time zero; drilling of the borehole between the two rooms at 5.7 years; and 2 years of post-drilling response. An all salt configuration was used in the calculation. The 1984 Waste Isolation Pilot Plant (WIPP) reference elastic-secondary creep law, with reduced elastic moduli, was used to model the creeping response of the salt. Results show that after mining of the rooms andmore » cross drift a relatively high von Mises stress state exists around the perimeter of the pillar. However, by 5.7 years, or immediately prior to drilling of the borehole, the pillar has relaxed to an almost uniform von Mises stress of about 7--8 MPa. After the borehole is drilled, a relatively high von Mises stress field is once again set up in the immediate vicinity of the hole. This drives the creep closure of the borehole. The hole closes more in the vertical direction than in the horizontal direction, resulting in ovalling of the hole. At the end of the simulation, the von Mises stress around the borehole is still higher than that in the remained of the pillar. Thus, the closure rates are relatively high at the end of the simulation time.« less

Waste Isolation Pilot Plant site environmental report, for calendar year 1995

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

The U.S. Department of Energy (DOE) Order 5400.1 General Environmental Protection Program, requires DOE facilities, that conduct environmental protection programs, to annually prepare a Site Environmental Report (SER). The purpose of the SER is to provide an abstract of environmental assessments conducted in order to characterize site environmental management performance, to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit. The content of this SER is not restricted to a synopsis of the required data, in addition, information pertaining to new and continued monitoring and compliance activities during the 1995 calendar yearmore » are also included. Data contained in this report are derived from those monitoring programs directed by the Waste Isolation Pilot Plant (WIPP) Environmental Monitoring Plan (EMP). The EMP provides inclusive guidelines implemented to detect potential impacts to the environment and to establish baseline measurements for future environmental evaluations. Surface water, groundwater. air, soil, and biotic matrices are monitored for an array of radiological and nonradiological factors. The baseline radiological surveillance program encompasses a broader geographic area that includes nearby ranches, villages, and cities. Most elements of nonradiological assessments are conducted within the geographic vicinity of the WIPP site.« less

Hazards Associated with Legacy Nitrate Salt Waste Drums Managed under the Container Isolation Plan

DOE Office of Scientific and Technical Information (OSTI.GOV)

Funk, David John; Clark, David Lewis

At present, there are 29 drums of nitrate waste salts (oxidizers with potentially acidic liquid bearing RCRA characteristics D001 and D002) that are awaiting processing, specifically to eliminate these characteristics and to allow for ultimate disposition at WIPP. As a result of the Feb. 14th, 2014 drum breach at WIPP, and the subsequent identification of the breached drum as a product ofLANL TRU waste disposition on May 15th, 2014, these 29 containers were moved into the Perrnacon in Dome 231 at TA-54 Area G, as part of the New Mexico Environment Department (NMED) approved container isolation plan. The plan ismore » designed to mitigate hazards associated with the nitrate salt bearing waste stream. The purpose of this document is to articulate the hazards associated with un-remediated nitrate salts while in storage at LANL. These hazards are distinctly different from the Swheat-remediated nitrate salt bearing drums, and this document is intended to support the request to remove the un-remediated drums from management under the container isolation plan. Plans to remediate and/or treat both of these waste types are being developed separately, and are beyond the scope of this document.« less

Resource Conservation and Recovery Act, Part B Permit Application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 5, Chapter D, Appendix D1 (conclusion), Revision 3

DOE Office of Scientific and Technical Information (OSTI.GOV)

Cook, Neville G.W.; Heuze, Francois E.; Miller, Hamish D.S.

1993-03-01

The reference design for the underground facilities at the Waste Isolation Pilot Plant was developed using the best criteria available at initiation of the detailed design effort. These design criteria are contained in the US Department of Energy document titled Design Criteria, Waste Isolation Pilot Plant (WIPP). Revised Mission Concept-IIA (RMC-IIA), Rev. 4, dated February 1984. The validation process described in the Design Validation Final Report has resulted in validation of the reference design of the underground openings based on these criteria. Future changes may necessitate modification of the Design Criteria document and/or the reference design. Validation of the referencemore » design as presented in this report permits the consideration of future design or design criteria modifications necessitated by these changes or by experience gained at the WIPP. Any future modifications to the design criteria and/or the reference design will be governed by a DOE Standard Operation Procedure (SOP) covering underground design changes. This procedure will explain the process to be followed in describing, evaluating and approving the change.« less

NDA Batch 2002-13

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hollister, R

QC sample results (daily background check drum and 100-gram SGS check drum) were within acceptance criteria established by WIPP's Quality Assurance Objectives for TRU Waste Characterization. Replicate runs were performed on drum LL85501243TRU. Replicate measurement results are identical at the 95% confidence level as established by WIPP criteria. HWM NCAR No. 02-1000168 issued on 17-Oct-2002 regarding a partially dislodged Cd sheet filter on the HPGe coaxial detector. This physical geometry occurred on 01-Oct-2002 and was not corrected until 10-Oct-2002, during which period is inclusive of the present batch run of drums. Per discussions among the Independent Technical Reviewer, Expert Reviewermore » and the Technical QA Supervisor, as well as in consultation with John Fleissner, Technical Point of Contact from Canberra, the analytical results are technically reliable. All QC standard runs during this period were in control. Data packet for SGS Batch 2002-13 generated using passive gamma-ray spectroscopy with the Pu Facility SGS unit is technically reasonable. All QC samples are in compliance with establiShed control limits. The batch data packet has been reviewed for correctness, completeness, consistency and compliance with WIPP's Quality Assurance Objectives and determined to be acceptable.« less

WIPP Remote-Handled TRU Waste Program Update

DOE Office of Scientific and Technical Information (OSTI.GOV)

Most, W.; Kehrman, B.

2006-07-01

There are two major regulatory approval milestones necessary in order to commence disposal operations for remote-handled transuranic (RH TRU) waste at the Waste Isolation Pilot Plant (WIPP)-the RH TRU hazardous waste permit modification request [1] and the radiological characterization plan [2]. One of those milestones has been achieved. The US Environmental Protection Agency (EPA) issued its final decision to approve the Department of Energy's (DOE) RH TRU radiological characterization plan along with the RH TRU Waste Characterization Program Implementation Plan [3], on March 26, 2004. The RH TRU hazardous waste permit modification request still awaits agency approval. In EPA's decisionmore » to approve the DOE's RH TRU radiological characterization plan, the EPA also set forth the process for approving site-specific RH TRU waste characterization programs. Included in the March 29, 2005, RH TRU second Notice of Deficiency [4] (NOD) on the Class 3 Permit Modification Request for RH TRU Waste, the New Mexico Environment Department (NMED) requested that the Permittees combine their responses for the RH TRU Waste NOD with the Section 311 permit modification request NOD. The Combined Response Document was submitted April 28, 2005 [5]. Another NOD [6] was issued by the NMED on September 1, 2005, to clarify the Permittees' proposal and submit these clarifications to the administrative record. Combining both the chap. 311 [7] and RH TRU waste permit modification requests allows for both the regulator and Permittees to expedite action on the modification requests. The Combined Response Document preserves human resources and costs by having only one administrative process for both modification requests. Facility readiness requirements of the RH TRU waste final permit [8] must be implemented to declare that the WIPP is ready to receive RH TRU waste for storage and disposal. To demonstrate readiness, the WIPP is preparing for an Operational Readiness Review (ORR) of the RH TRU waste management equipment, system, and procedures. Required by DOE Order, the ORR demonstrates the capability of managing RH TRU waste. The Management and Operating Contractor (MOC) for the WIPP must first perform a Line Management Assessment. Upon successful completion of the Line Management Assessment, the MOC performs the Contractor ORR and presents the results to the local DOE office. At that time, the local DOE office performs its own ORR to declare readiness to DOE Headquarters. (authors)« less

Department of Energy Operational Readiness Review for the Waste Isolation Pilot Plant

DOE Office of Scientific and Technical Information (OSTI.GOV)

None, None

The U.S. Department of Energy (DOE) has completed an Operational Readiness Review (ORR) for the restart of Contact Handled (CH) waste emplacement at the Waste Isolation Pilot Plant (WIPP) located near Carlsbad, New Mexico. The ORR team assessed the readiness of Nuclear Waste Partnership, LLC (NWP) to manage and perform receipt through CH waste emplacement, and associated waste handling and management activities, including the ability of the National TRU Program (NTP) to evaluate the waste currently stored at the WIPP site against the revised and enhanced Waste Acceptance Criteria (WAC). Field work for this review began on November 14, 2015more » and was completed on November 30, 2016. The DOE ORR was conducted in accordance with the Department of Energy Operational Readiness Review Implementation Plan for the Waste Isolation Pilot Plant, dated November 8, 2016, and DOE Order 425.1D, Verification of Readiness to Start Up or Restart Nuclear Facilities. The review activities included personnel interviews, record reviews, direct observation of operations and maintenance demonstrations, and observation of multiple operational and emergency drills/exercises. The DOE ORR also evaluated the adequacy of the contractor’s ORR (CORR) and the readiness of the DOE Carlsbad field Office (CBFO) to oversee the startup and execution of CH waste emplacement activities at the WIPP facility. The WIPP facility is categorized as a Hazard Category 2 DOE Nonreactor Nuclear Facility for all surface and Underground (UG) operations per DOE-STD-1027-92, Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports. In addition, the WIPP experienced two events in February, 2014 that resulted in Accident Investigations being performed in accordance with the requirements of DOE Order 225.1B, Accident Investigations. Based upon the results of the accident investigations and hazard categorization of the facility, the team placed significant emphasis on the following areas: fire protection, emergency preparedness, radiological protection, nuclear safety, and operations. The identification of specific focus areas was not intended to diminish the importance of other areas of the review, but to ensure that these areas received a particularly thorough and in-depth evaluation due to their significance with respect to the safe operation of the facility.« less

Radiation release at the nation's only operating deep geological repository--an independent monitoring perspective.

PubMed

Thakur, P; Ballard, S; Hardy, R

2014-11-04

Recent incidents at the nation's only operating deep geologic nuclear waste repository, the Waste Isolation Pilot Plant (WIPP), resulted in the release of americium and plutonium from one or more defense-related transuranic (TRU) waste containers into the environment. WIPP is a U.S. Department of Energy mined geologic repository that has been in operation since March, 1999. Over 85,000 m3 of waste in various vented payload containers have been emplaced in the repository. The primary radionuclides within the disposed waste are 239+240Pu and 241Am, which account for more than 99% of the total TRU radioactivity disposed and scheduled for disposal in the repository. For the first time in its 15 years of operation, there was an airborne radiation release from the WIPP at approximately 11:30 PM Mountain Standard Time (MST) on Friday, February 14, 2014. The radiation release was likely caused by a chemical reaction inside a TRU waste drum that contained nitrate salts and organic sorbent materials. In a recent news release, DOE announced that photos taken of the waste underground showed evidence of heat and gas pressure resulting in a deformed lid, in material expelled through that deformation, and in melted plastic and rubber and polyethylene in the vicinity of that drum. Recent entries into underground Panel 7 have confirmed that at least one waste drum containing a nitrate salt bearing waste stream from Los Alamos National Laboratory was breached underground and was the most likely source of the release. Further investigation is underway to determine if other containers contributed to the release. Air monitoring across the WIPP site intensified following the first reports of radiation detection underground to ascertain whether or not there were releases to the ground surface. Independent analytical results of air filters from sampling stations on and near the WIPP facility have been released by us at the Carlsbad Environmental Monitoring & Research Center and confirmed trace amounts of 241Am and 239+240Pu, at ratios reflecting the suspect waste stream. The highest activity detected offsite was 115.2 μBq/m3 for 241Am and 10.2 μBq/m3 for 239+240 Pu. These concentrations in air were very small, localized, and below any level of public health or environmental concern.

A Safety Case Approach for Deep Geologic Disposal of DOE HLW and DOE SNF in Bedded Salt - 13350

DOE Office of Scientific and Technical Information (OSTI.GOV)

Sevougian, S. David; MacKinnon, Robert J.; Leigh, Christi D.

2013-07-01

The primary objective of this study is to investigate the feasibility and utility of developing a defensible safety case for disposal of United States Department of Energy (U.S. DOE) high-level waste (HLW) and DOE spent nuclear fuel (SNF) in a conceptual deep geologic repository that is assumed to be located in a bedded salt formation of the Delaware Basin [1]. A safety case is a formal compilation of evidence, analyses, and arguments that substantiate and demonstrate the safety of a proposed or conceptual repository. We conclude that a strong initial safety case for potential licensing can be readily compiled bymore » capitalizing on the extensive technical basis that exists from prior work on the Waste Isolation Pilot Plant (WIPP), other U.S. repository development programs, and the work published through international efforts in salt repository programs such as in Germany. The potential benefits of developing a safety case include leveraging previous investments in WIPP to reduce future new repository costs, enhancing the ability to effectively plan for a repository and its licensing, and possibly expediting a schedule for a repository. A safety case will provide the necessary structure for organizing and synthesizing existing salt repository science and identifying any issues and gaps pertaining to safe disposal of DOE HLW and DOE SNF in bedded salt. The safety case synthesis will help DOE to plan its future R and D activities for investigating salt disposal using a risk-informed approach that prioritizes test activities that include laboratory, field, and underground investigations. It should be emphasized that the DOE has not made any decisions regarding the disposition of DOE HLW and DOE SNF. Furthermore, the safety case discussed herein is not intended to either site a repository in the Delaware Basin or preclude siting in other media at other locations. Rather, this study simply presents an approach for accelerated development of a safety case for a potential DOE HLW and DOE SNF repository using the currently available technical basis for bedded salt. This approach includes a summary of the regulatory environment relevant to disposal of DOE HLW and DOE SNF in a deep geologic repository, the key elements of a safety case, the evolution of the safety case through the successive phases of repository development and licensing, and the existing technical basis that could be used to substantiate the safety of a geologic repository if it were to be sited in the Delaware Basin. We also discuss the potential role of an underground research laboratory (URL). (authors)« less

Report of Class II Survey and Testing of Cultural Resources at the WIPP (Waste Isolation Pilot Plant) Site at Carlsbad, New Mexico,

DTIC Science & Technology

1987-05-01

a ;-A.act! ye Cune led mcl.t. a Iong I l’ nlortheasternf p i- tcr of ; e s~ e e uA n it w,’a 0 .;Taq"eI t1bf td o tie re:’ p. *, a. ~: t I..c() rvf ...just starting so they maue extra money selling milk to the Lniners. Thv-y kept eight or ten dairy cows and a small hierd of cattle. Th-e famrilly herded

Report of biological investigations at the Los Medanos Waste Isolation Pilot Plant (WIPP) area of New Mexico during FY 1978

DOE Office of Scientific and Technical Information (OSTI.GOV)

Best, T.L.; Neuhauser, S.

The US Department of Energy is considering the construction of a Waste Isolation Pilot Plant (WIPP) in Eddy County, NM. This location is approximately 40 km east of Carlsbad, NM. Biological studies during FY 1978 were concentrated within a 5-mi radius of drill hole ERDA 9. Additional study areas have been established at other sites in the vicinity, e.g., the Gnome site, the salt lakes and several stations along the Pecos River southward from Carlsbad, NM, to the dam at Red Bluff Reservoir in Texas. The precise locations of all study areas are presented and their biology discussed.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Weaver, Douglas James

The mission of Waste Isolation Pilot Plant (WIPP) is to demonstrate the safe, environmentally sound, cost effective, permanent disposal of Transuranic (TRU) waste left from production of nuclear weapons.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

This permit application (Vol. 7) for the WIPP facility contains appendices related to the following information: Ground water protection; personnel; solid waste management; and memorandums concerning environmental protection standards.

Draft Title 40 CFR 191 compliance certification application for the Waste Isolation Pilot Plant. Volume 8: Appendices HYDRO, IRD, LTM, NUTS, PAR, PMR, QAPD, RBP

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

Geohydrologic data have been collected in the Los Medanos area at the US Department of Energy`s proposed Waste Isolation Pilot Plant (WIPP) site in southeastern New Mexico since 1975 as part of a study evaluating the feasibility of storing defense-associated nuclear wastes within the bedded salt of the Salado Formation of Permian age. Drilling and hydrologic testing have identified three principal water-bearing zones above the Salado Formation and one below that could potentially transport wastes to the biosphere if the proposed facility were breached. The zones above the Salado are the contact between the Rustler and Salado Formations and themore » Culebra and Magenta Dolomite Members of the Rustler Formation of Permian age. The zone below the Salado Formation consists of channel sandstones in the Bell Canyon Formation of the Permian Delaware Mountain Group. Determinations of hydraulic gradients, directions of flow, and hydraulic properties were hindered because of the negligible permeability of the water-bearing zones. Special techniques in drilling, well completion, and hydraulic testing have been developed to determine the hydrologic characteristics of these water-producing zones.« less

Resource Conservation and Recovery Act, Part B permit application [of the Waste Isolation Pilot Plant (WIPP)]. Volume 11, Chapter D, Appendix D4--Chapter D, Appendix D17: Revision 3

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1993-03-01

This volume contains appendices D4 through D17 which cover the following: Waste Isolation Pilot Plant site environmental report; ecological monitoring program at the Waste Isolation Pilot Plant; site characterization; regional and site geology and hydrology; general geology; dissolution features; ground water hydrology; typical carbon sorption bed efficiency; VOC monitoring plan for bin-room tests; chemical compatibility analysis of waste forms and container materials; probable maximum precipitation; WHIP supplementary roof support system room 1, panel 1; and corrosion risk assessment of the Waste Isolation Pilot Plant ``humid`` test bins.

Pretest reference calculation for the overtest for simulated defense high level waste (WIPP) Room B in situ experiment)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Morgan, H.S.; Stone, C.M.

A pretest reference calculation for the Overtest for Simulated Defense High-Level Waste (DHLW) or Room B experiment is presented in this report. The overtest is one of several large-scale, in-situ experiments currently under construction near Carlsbad, New Mexico at the site of the Waste Isolation Pilot Plant (WIPP). Room B, a single isolated room in the underground salt formation, is to be subjected to a thermal load of approximately four times the areal heat output anticipated for a future repository with DHLW. The load will be supplied 3 years by canister heaters placed in the floor. Room B is heavilymore » instrumented for monitoring both temperature increases due to the thermal loading and deformations due to creep of the salt. Data from the experiment are not available at the present time, but the measurements will eventually be compared to the results presented to assess and improve thermal and mechanical modeling capabilities for the WIPP. The thermal/structural model used here represents the state of the art at the present time. A large number of plots are included since an appropriate result is presented for every Room B gauge location. 81 figs., 4 tabs.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Green, D.W.; Heinrich, R.R.; Graczyk, D.G.

The ACL activities covered IFR fuel reprocessing, corium-concrete interactions, environmental samples, wastes, WIPP support, Advanced Photon Source, H-Tc superconductors, EBWR vessel, soils, illegal drug detection, quality control, etc.

Column Experiments for Radionuclide Adsorption Studies of the Culebra Dolomite: Retardation Parameter Estimation for Non-Eluted Actinide Species

DOE Office of Scientific and Technical Information (OSTI.GOV)

Brown, G.O.; Lucero, D.A.; Perkins, W.G.

The U.S. Department of Energy (DOE) has been developing a nuclear waste disposal facility, the Waste Isolation Pilot Plant (WIPP), located approximately 42 km east of Carlsbad, New Mexico. The WIPP is designed to demonstrate the safe disposal of transuranic wastes produced by the defense nuclear-weapons program. Performance assessment analyses (U.S. DOE, 1996) indicate that human intrusion by inadvertent and intermittent drilling for resources provide the only credible mechanisms for significant releases of radionuclides horn the disposal system. These releases may occur by five mechanisms: (1) cuttings, (2) cavings, (3) spallings, (4) direct brine releases, and (5) long-term brine releases.more » The first four mechanisms could result in immediate release of contaminant to the accessible environment. For the last mechanism, migration pathways through the permeable layers of rock above the Salado are important, and major emphasis is placed on the Culebra Member of the Rustler Formation because this is the most transmissive geologic layer in the disposal system. For reasons of initial quantity, half-life, and specific radioactivity, certain isotopes of Th, U, Am, and Pu would dominate calculated releases from the WIPP. In order to help quanti~ parameters for the calculated releases, radionuclide transport experiments have been carried out using five intact-core columns obtained from the Culebra dolomite member of the Rustler Formation within the Waste Isolation Pilot Plant (WIPP) site in southeastern New Mexico. This report deals primarily with results of mathematical analyses related to the retardation of %J%, 24%, and 24'Am in two of these cores (B-Core - VPX26-11A and C-Core - VPX28-6C). All B-Core transport experiments were done using Culebra-simukmt brine relevant to the core recovery location (the WIPP air-intake shaft - AIS). Most experiments with C-Core were done with AIS brine with some admixture of a brine composition (ERDA-6) that simulated deeper formation brines. No significant changes in transport behavior were observed for changes in brine. Hydraulic characteristics (i.e., apparent porosity and apparent dispersion coefficient) for the cores were obtained via experiments using conservative tracer `Na. Elution experiments carried out over periods of a few days with tracers `*U and %Np indicated that these tracers were weakly retarded as indicated by delayed elution of these species. Elution experiments with tracers `%, 24'Pu, and 24'Ani were performed, but no elution of any of these species was observed in any flow experiment to date, including experiments of up to two years duration. However, B-Core was subjected to tomographic analysis from which a retardation factor can be inferred for%. Moreover, the fact of non- elution for 24*Pu and 24'Am after more than two years brine flow through C-Core can be coupled with the minimum detectable activity for each of these species to compute minimum retardation factors in C-Core. The retardation factors for all three species can then be coupled with the apparent hydraulic characteristics to estimate an apparent minimum solutionhock distribution coefficient, &, for each actinide. The specific radionuclide isotopes used in these experiments were chosen to facilitate analysis. Even though these isotopes are not necessarily the same as those that are most important to WIPP performance, they are isotopes of the same elements, and . their chemical and transport properties are therefore identical to those of isotopes in the WIPP inventory. The retardation factors and & values deduced from experimental results strongly support the contention that sorption in the Culebra provides an effective barrier to release of Th, Pu, and Am during the regulatory period.« less

Reconstructing the Chronology of Supernovae: Determining Major Variations in the History of the Cosmic-ray Flux Incident on the Earth's Surface by Measuring the Concentration of 22Ne in Halite

NASA Astrophysics Data System (ADS)

Nahill, N. D.; Giegengack, R.; Lande, K.; Omar, G.

2008-12-01

We plan to measure the inventory of cosmogenically produced 22Ne atoms preserved in the mineral lattice of halite in deposits of rock salt, and to use that inventory to measure variations in the cosmic-ray flux to enable us to reconstruct the history of supernovae. Bedded rock salt consists almost entirely of the mineral halite (NaCl). Any neon trapped in the halite crystals during precipitation is primarily 20Ne, with a 22Ne concentration of 9% or less. Any neon resulting from cosmic-ray interactions with 23Na is solely 22Ne; therefore, 22Ne atoms in excess of 9% of the total neon are cosmogenic in origin. Measurement of the 22Ne inventory in halite from deposits covering a range of geologic ages may enable us to document the systematic growth of 22Ne through geologic time and, thus, establish the cosmic-ray flux and a chronology of supernovae. The cosmic-ray flux is attenuated in direct proportion to the mass of material overlying a halite deposit. To adjust the 22Ne inventory to account for that attenuation, we must reconstruct the post-depositional history of accumulation and removal of superjacent sediment for each halite deposit we study. As an example of our procedure, we reconstruct here the shielding history of the Permian halite deposit, the Salado Formation, Delaware Basin, New Mexico. The stratigraphy of the Delaware Basin has been well documented via exploration and production wells drilled in search of oil and gas, exploration boreholes associated with potash mining, and comprehensive geologic site assessment of the DOE Waste Isolation Pilot Plant (WIPP). WIPP is a subsurface repository for the permanent disposal of transuranic wastes, located in southeastern New Mexico, 42 km east of Carlsbad and approximately 655 m beneath the surface in the Salado Fm. The Salado Fm is part of the Late Permian Ochoan Series, and consists of 1) a lower member, 2) the McNutt Potash Zone, and 3) an upper member. WIPP lies between marker bed (MB)139 and MB136 in the lower member of the Salado Fm. MB139 forms the floor of WIPP. At WIPP, the Rustler Fm and the Dewey Lake Red Beds, both Ochoan in age, directly overlie the Salado Fm. The Dewey Lake marks the end of Permian deposition. The Santa Rosa Fm of the Late Triassic (late Carnian) Chinle Group lies unconformably over the Ochoan series. The unconformity represents a depositional gap of at least 25 million years. Another major unconformity, representing at least 210 million years, separates the Santa Rosa Fm from the overlying Miocene-Pliocene Ogallala Fm. The Pleistocene Gatuña Fm conformably overlies the Ogallala, but in many places it unconformably overlies Ochoan Permian rocks. Strata from the Jurassic to Late Tertiary do not occur at WIPP. The stratigraphic section at WIPP is well documented, but we must account for the column of rock that was deposited over the site and subsequently removed by erosion since deposition of the Salado halite. From hydrocarbon maturation-data, Hills (1984) estimated the missing overburden as 1,200 m. From stratigraphic inferences, Powers and Holt (1995) estimated that 400 m of rock have been removed by erosion since deposition of the Salado Fm. Using thermal indicators such as vitrinite reflectance, fission-track analysis, U/Th-He, 40Ar/39Ar, and fluid-inclusion analysis, we plan to constrain the thermal history at the site. We will reconstruct the mass of material that accumulated above the Salado Formation, and the period of time during which that cover remained in place.

Thermodynamic Properties of Magnesium Chloride Hydroxide Hydrate (Mg3Cl(OH)5:4H2O, Phase 5), and Its importance to Nuclear Waste Isolation in Geological Repositories in Salt Formations

NASA Astrophysics Data System (ADS)

Xiong, Y.; Deng, H.; Nemer, M. B.; Johnsen, S.

2009-12-01

MgO (bulk, pure MgO corresponding to the mineral periclase) is the only engineered barrier certified by the Environmental Protection Agency for emplacement in the Waste Isolation Pilot Plant (WIPP) in the US, and an Mg(OH)2-based engineered barrier (bulk, pure Mg(OH)2 corresponding to brucite) is to be employed in the Asse repository in Germany. Both the WIPP and the Asse are located in salt formations. The WIPP is a U.S. Department of Energy geological repository being used for the permanent disposal of defense-related transuranic waste (TRU waste). The repository is 655 m below the surface, and is situated in the Salado Formation, a Permian salt bed mainly composed of halite, and of lesser amounts of polyhalite, anhydrite, gypsum, magnesite, clays and quartz. The WIPP Generic Weep Brine (GWB), a Na-Mg-Cl dominated brine, is associated with the Salado Formation. The previous vendor for MgO for the WIPP was Premier Chemicals and the current vendor is Martin Marietta Materials. Experimental studies of both Premier MgO and Martin Marietta MgO with the GWB at SNL indicate the formation of magnesium chloride hydroxide hydrate, Mg3Cl(OH)5:4H2O, termed as phase 5. However, this important phase is lacking in the existing thermodynamic database. In this study, the solubility constant of phase 5 is determined from a series of solubility experiments in MgCl2-NaCl solutions. The solubility constant at 25 oC for the following reaction, Mg3Cl(OH)5:4H2O + 5H+ = 3Mg2+ + 9H2O(l) + Cl- is recommended as 43.21±0.33 (2σ) based on the Specific Interaction Theory (SIT) model for extrapolation to infinite dilution. The log K obtained via the Pitzer equations is identical to the above value within the quoted uncertainty. The Gibbs free energy and enthalpy of formation for phase 5 at 25 oC are derived as -3384±2 (2σ) kJ mol-1 and -3896±6 (2σ) kJ mol-1, respectively. The standard entropy and heat capacity of phase 5 at 25 oC are estimated as 393±20 J mol-1 K-1 and 374±19 J mol-1 K-1, respectively. Phase 5, and its similar phase, phase 3 (Mg2Cl(OH)3:4H2O), could have a significant role in influencing the geochemical conditions in geological repositories for nuclear waste in salt formations where MgO or brucite is employed as engineered barriers, when Na-Mg-Cl dominated brines react with MgO or brucite. Based on our solubility constant for phase 5 in combination with the literature value for phase 3, we predict that the composition for the invariant point of phase 5 and phase 3 would be mMg = 1.70 and pmH = 8.93 in the Mg-Cl binary system. The recent WIPP Compliance Recertification Application PA Baseline Calculations indicate that phase 5 instead of phase 3 is indeed a stable phase when GWB equilibrates with actinide-source-term phases, brucite, magnesium carbonates, halite and anhydrite. 1. This research is funded by WIPP programs administered by the U.S. Department of Energy. 2. Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy’s National Nuclear Security Administration under contract DE-AC04-94AL85000.

Complexation of Nd(III) with tetraborate ion and its effect on actinide (III) solubility in WIPP brine

DOE Office of Scientific and Technical Information (OSTI.GOV)

Borkowski, Marian; Richmann, Michael K; Reed, Donald T

2010-01-01

The potential importance of tetraborate complexation on lanthanide(III) and actinide(III) solubility is recognized in the literature but a systematic study of f-element complexation has not been performed. In neodymium solubility studies in WIPP brines, the carbonate complexation effect is not observed since tetraborate ions form a moderately strong complex with neodymium(III). The existence of these tetraborate complexes was established for low and high ionic strength solutions. Changes in neodymium(III) concentrations in undersaturation experiments were used to determine the neodymium with tetraborate stability constants as a function of NaCl ionic strength. As very low Nd(III) concentrations have to be measured, itmore » was necessary to use an extraction pre-concentration step combined with ICP-MS analysis to extend the detection limit by a factor of 50. The determined Nd(III) with borate stability constants at infinite dilution and 25 C are equal to log {beta}{sub 1} = 4.55 {+-} 0.06 using the SIT approach, equal to log {beta}{sub 1} = 4.99 {+-} 0.30 using the Pitzer approach, with an apparent log {beta}{sub 1} = 4.06 {+-} 0.15 (in molal units) at I = 5.6 m NaCl. Pitzer ion-interaction parameters for neodymium with tetraborate and SIT interaction coefficients were also determined and reported.« less

Sandia Review of High Bridge Associates Report: Comparison of Plutonium Disposition Alternatives: WIPP Diluted Plutonium Storage and MOX Fuel Irradiation

DOE Office of Scientific and Technical Information (OSTI.GOV)

Shoemaker, Paul E.; Hardin, Ernest; Park, HeeHo Daniel

The subject report from High Bridge Associates (HBA) was issued on March 2, 2016, in reaction to a U.S. Department of Energy (DOE) program decision to pursue down-blending of surplus Pu and geologic disposal at the Waste Isolation Pilot Plant (WIPP). Sandia National Laboratories was requested by the DOE to review the technical arguments presented in the HBA report. Specifically, this review is organized around three technical topics: criticality safety, radiological release limits, and thermal impacts. Questions raised by the report pertaining to legal and regulatory requirements, safeguards and security, international agreements, and costing of alternatives, are beyond the scopemore » of this review.« less

1979 New Mexico legislative session: energy issues and legislation. [WIPP

DOE Office of Scientific and Technical Information (OSTI.GOV)

Barsumian, L.; Vandevender, S.G.

1979-10-01

This report is an account of the energy legislation and associated issues considered during the 1979 session of the 34th New Mexico Legislature. The session's major issue was the federal study of a proposed nuclear Waste Isolation Pilot Plant (WIPP) in New Mexico. A large proportion of time and effort was spent on resolving the state's formal position toward the federal project. However, other energy concerns were also significant even though they were neither as controversial nor as visible as the primary issue. The two most important laws enacted were the Radioactive Waste Consultation Act and the Radioactive Waste Transportationmore » Act. The Legislature considered 47 other energy-related bills, of which 17 were enacted.« less

Biennial Environmental Compliance Report (2010-2012)

EPA Pesticide Factsheets

This Biennial Environmental Compliance Report (BECR) documents United States (U.S.) Department of Energy (DOE) compliance with environmental regulations applicable to the Waste Isolation Pilot Plant (WIPP) facility.

TRU Waste Management Program cost/schedule optimization analysis

DOE Office of Scientific and Technical Information (OSTI.GOV)

Detamore, J.A.; Raudenbush, M.H.; Wolaver, R.W.

1985-10-01

The cost/schedule optimization task is a necessary function to insure that program goals and plans are optimized from a cost and schedule aspect. Results of this study will offer DOE information with which it can establish, within institutional constraints, the most efficient program for the long-term management and disposal of contact handled transuranic waste (CH-TRU). To this end, a comprehensive review of program cost/schedule tradeoffs has been made, to identify any major cost saving opportunities that may be realized by modification of current program plans. It was decided that all promising scenarios would be explored, and institutional limitations to implementationmore » would be described. Since a virtually limitless number of possible scenarios can be envisioned, it was necessary to distill these possibilities into a manageable number of alternatives. The resultant scenarios were described in the cost/schedule strategy and work plan document. Each scenario was compared with the base case: waste processing at the originating site; transport of CH-TRU wastes in TRUPACT; shipment of drums in 6-Packs; 25 year stored waste workoff; WIPP operational 10/88, with all sites shipping to WIPP beginning 10/88; and no processing at WIPP. Major savings were identified in two alternate scenarios: centralize waste processing at INEL and eliminate rail shipment of TRUPACT. No attempt was made to calculate savings due to combination of scenarios. 1 ref., 5 figs., 1 tab. (MHB)« less

Processing Plan for Potentially Reactive/Ignitable Remote Handled Transuranic Waste at the Idaho Cleanup Project - 12090

DOE Office of Scientific and Technical Information (OSTI.GOV)

Troescher, Patrick D.; Hobbes, Tammy L.; Anderson, Scott A.

Remote Handle Transuranic (RH-TRU) Waste generated at Argonne National Laboratory - East, from the examination of irradiated and un-irradiated fuel pins and other reactor materials requires a detailed processing plan to ensure reactive/ignitable material is absent to meet WIPP Waste Acceptance Criteria prior to shipping and disposal. The Idaho Cleanup Project (ICP) approach to repackaging Lot 2 waste and how we ensure prohibited materials are not present in waste intended for disposal at Waste Isolation Pilot Plant 'WIPP' uses an Argon Repackaging Station (ARS), which provides an inert gas blanket. Opening of the Lot 2 containers under an argon gasmore » blanket is proposed to be completed in the ARS. The ARS is an interim transition repackaging station that provides a mitigation technique to reduce the chances of a reoccurrence of a thermal event prior to rendering the waste 'Safe'. The consequences, should another thermal event be encountered, (which is likely) is to package the waste, apply the reactive and or ignitable codes to the container, and store until the future treatment permit and process are available. This is the same disposition that the two earlier containers in the 'Thermal Events' were assigned. By performing the initial handling under an inert gas blanket, the waste can sorted and segregate the fines and add the Met-L-X to minimize risk before it is exposed to air. The 1-gal cans that are inside the ANL-E canister will be removed and each can is moved to the ARS for repackaging. In the ARS, the 1-gal can is opened in the inerted environment. The contained waste is sorted, weighed, and visually examined for non compliant items such as unvented aerosol cans and liquids. The contents of the paint cans are transferred into a sieve and manipulated to allow the fines, if any, to be separated into the tray below. The fines are weighed and then blended with a minimum 5:1 mix of Met-L-X. Other debris materials found are segregated from the cans into containers for later packaging. Recoverable fissile waste material (Fuel and fuel-like pieces) suspected of containing sodium bonded pieces) are segregated and will remain in the sieve or transferred to a similar immersion basket in the ARS. The fuel like pieces will be placed into a container with sufficient water to cover the recoverable fissile waste. If a 'reactive characteristic' is present the operator will be able to observe the formation of 'violent' hydrogen gas bubbles. When sodium bonded fuel-like pieces are placed in water the expected reaction is a non-violent reaction that does not meet the definition of reactivity. It is expected that there will be a visible small stream of bubbles present if there is any sodium-bonded fuel-like piece placed in the water. The test will be completed when there is no reaction or the expected reaction is observed..At that point, the fuel like pieces complete the processing cycle in preparation for characterization and shipment to WIPP. If a violent reaction occurs, the fuel-like pieces will be removed from the water, split into the required fissile material content, placed into a screened basket in a 1 gallon drum and drummed out of the hot cell with appropriate RCRA codes applied and placed into storage until sodium treatment is available. These 'violent' reactions will be evidenced by gas bubbles being evolved at the specimen surface where sodium metal is present. The operators will be trained to determine if the reaction is 'violent' or 'mild'. If a 'violent' reaction occurs, the sieve will be immediately removed from the water, placed in a 1 gallon paint can, canned in the argon cover gas and removed from the hot cell to await a future treatment. If the reaction is 'mild', the sieve will then be removed from the water; the material weighed for final packaging and allowed to dry by air exposure. Lot 2 waste cans can be opened, sorted, processed, and weighed while mitigating the potential of thermal events that could occur prior to exposing to air. Exposure to air is a WIPP compliance step demonstrating the absence of reactive or ignitable characteristics. (authors)« less

Brine and Gas Flow Patterns Between Excavated Areas and Disturbed Rock Zone in the 1996 Performance Assessment for the Waste Isolation Pilot Plant for a Single Drilling Intrusion that Penetrates Repository and Castile Brine Reservoir

DOE Office of Scientific and Technical Information (OSTI.GOV)

ECONOMY,KATHLEEN M.; HELTON,JON CRAIG; VAUGHN,PALMER

1999-10-01

The Waste Isolation Pilot Plant (WIPP), which is located in southeastern New Mexico, is being developed for the geologic disposal of transuranic (TRU) waste by the U.S. Department of Energy (DOE). Waste disposal will take place in panels excavated in a bedded salt formation approximately 2000 ft (610 m) below the land surface. The BRAGFLO computer program which solves a system of nonlinear partial differential equations for two-phase flow, was used to investigate brine and gas flow patterns in the vicinity of the repository for the 1996 WIPP performance assessment (PA). The present study examines the implications of modeling assumptionsmore » used in conjunction with BRAGFLO in the 1996 WIPP PA that affect brine and gas flow patterns involving two waste regions in the repository (i.e., a single waste panel and the remaining nine waste panels), a disturbed rock zone (DRZ) that lies just above and below these two regions, and a borehole that penetrates the single waste panel and a brine pocket below this panel. The two waste regions are separated by a panel closure. The following insights were obtained from this study. First, the impediment to flow between the two waste regions provided by the panel closure model is reduced due to the permeable and areally extensive nature of the DRZ adopted in the 1996 WIPP PA, which results in the DRZ becoming an effective pathway for gas and brine movement around the panel closures and thus between the two waste regions. Brine and gas flow between the two waste regions via the DRZ causes pressures between the two to equilibrate rapidly, with the result that processes in the intruded waste panel are not isolated from the rest of the repository. Second, the connection between intruded and unintruded waste panels provided by the DRZ increases the time required for repository pressures to equilibrate with the overlying and/or underlying units subsequent to a drilling intrusion. Third, the large and areally extensive DRZ void volumes is a significant source of brine to the repository, which is consumed in the corrosion of iron and thus contributes to increased repository pressures. Fourth, the DRZ itself lowers repository pressures by providing storage for gas and access to additional gas storage in areas of the repository. Fifth, given the pathway that the DRZ provides for gas and brine to flow around the panel closures, isolation of the waste panels by the panel closures was not essential to compliance with the U.S. Environment Protection Agency's regulations in the 1996 WIPP PA.« less

Waste isolation pilot plant (WIPP) borehole plugging program description

DOE Office of Scientific and Technical Information (OSTI.GOV)

Christensen, C.L.; Hunter, T.O.

1979-08-01

The tests and experiments described attempt to provide a mix of borehole (with limited access) and in-mine (with relatively unlimited access) environments in which assessment of the various issues involved can be undertaken. The Bell Canyon Test provides the opportunity to instrument and analyze a plug in a high pressure region. The Shallow Hole Test permits application of best techniques for plugging and then access to both the top and bottom of the plug for further analysis. The Diagnostic Test Hole permits recovery of bench scale size samples for analysis and establishes an in-borehole laboratory in which to conduct testingmore » and analysis in all strata from the surface into the salt horizon. The additional in mine experiments provide the opportunity to investigate in more detail specific effects on plugs in the salt region and allows evaluation of instrumentation systems.« less

DOE's Remote-Handled TRU Waste Characterization Program: Implementation Plan

EPA Pesticide Factsheets

Remote-handled (RH) transuranic (TRU) waste characterization, which involves obtaining chemical, radiological, and physical data, is a primary component of ensuring compliance of the Waste Isolation Pilot Plant (WIPP) with regulatory requirements.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ward, Anderson; Basabilvazo, George T.

The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2016 (ASER) is to provide the information required by U.S. Department of Energy (DOE) Order 231.1B, Environment, Safety, and Health Reporting. The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC) maintain and preserve the environmental resources at the WIPP facility. DOE Order 231.1B; DOE Order 436.1, Departmental Sustainability; and DOE Order 458.1, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public andmore » workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1B, which requires DOE facilities to submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer.« less

Sandia and the Waste Isolation Pilot Plant, 1974--1999

DOE Office of Scientific and Technical Information (OSTI.GOV)

MORA,CARL J.

2000-04-11

Engineers have learned to design and build big projects, which certainly describes the WIPP project, but also includes defense projects, highway networks, space exploration, the Internet, etc., through what has been called a messily complex embracing of contradictions. When something massive and complicated has to be built these days, it leads to a protracted political process in which every special interest makes a stand, lobbyists exert what influence they can, lawmakers bicker, contractors change things, Congress struggles with costs, environmentalists hold things up--and this is good. It may seem amazing that anything gets done, but when it does, everyone hasmore » had their say. It's an intensely democratic, even if expensive and time-consuming, process. The corporate historian of Sandia National Laboratories presents a unique background of the WIPP project and Sandia's part in it.« less

Hanford solid-waste handling facility strategy

NASA Astrophysics Data System (ADS)

Albaugh, J. F.

1982-05-01

Prior to 1970, transuranic (TRU) solid waste was disposed of at Hanford by shallow land burial. Since 1970, TRU solid waste has been stored in near surface trenches designed to facilitate retrieval after twenty year storage period. Current strategy calls for final disposal in a geologic repository. Funding permitting, in 1983, certification of newly generated TRU waste to the Waste Isolation Pilot Plant (WIPP) criteria for geologic disposal will be initiated. Certified and uncertified waste will continue to be stored at Hanford in retrievable storage until a firm schedule for shipment to WIPP is developed. Previously stored wastes retrieved for geologic disposal and newly generated uncertified waste requires processing to assure compliance with disposal criteria. A facility to perform this function is being developed. A study to determine the requirements of this Waste Receiving and Processing (WRAP) Facility is currently being conducted.

Durability of concrete materials in high-magnesium brine

DOE Office of Scientific and Technical Information (OSTI.GOV)

Wakeley, L.D.; Poole, T.S.; Burkes, J.P.

1994-03-01

Cement pastes and mortars representing 11 combinations of candidate concrete materials were cast in the laboratory and monitored for susceptibility to chemical deterioration in high-magnesium brine. Mixtures were selected to include materials included in the current leading candidate concrete for seals at the Waste Isolation Pilot Plant (WIPP). Some materials were included in the experimental matrix to answer questions that had arisen during study of the concrete used for construction of the liner of the WIPP waste-handling shaft. Mixture combinations compared Class C and Class F fly ashes, presence or absence of an expansive component, and presence or absence ofmore » salt as a mixture component. Experimental conditions exposed the pastes and mortars to extreme conditions, those being very high levels of Mg ion and an effectively unlimited supply of brine. All pastes and mortars showed deterioration with brine exposure. In general, mortars deteriorated more extensively than the corresponding pastes. Two-inch cube specimens of mortar were not uniformly deteriorated, but showed obvious zoning even after a year in the brine, with a relatively unreacted zone remaining at the center of each cube. Loss of calcium from the calcium hydroxide of paste/aggregate interfaces caused measurable strength loss in the reacted zone comprising the outer portion of every mortar specimen. The current candidate mass concrete for WIPP seals includes salt as an initial component, and has a relatively closed initial microstructure. Both of these features contribute to its suitability for use in large placements within the Salado Formation.« less

Role of Brine Chemistry and Sorption in Potential Long-Term Storage of Radioactive Waste in Geologic Salt Formations: Experimental Evaluation of Sorption Parameters

NASA Astrophysics Data System (ADS)

Dittrich, T. M.; Emerson, H. P.; Michael, D. P.; Reed, D. T.

2016-12-01

Bedded geologic salt formations have been shown to have many favorable properties for the disposal of radioactive waste (i.e., reducing conditions, fracture healing). Performance assessment (PA) modeling for a 10,000 year period for the Waste Isolation Pilot Plant (WIPP) near Carlsbad, NM have predicted an extremely low risk of radioactive material reaching the surrounding environment after the 100 year period required for creep to seal the waste panels and access shafts. Human intrusion caused by drilling operations for oil and gas exploration is the main pathway of concern for environmental release of radioactive material due to pressurized brine pockets located within the salt formation below the repository. Our work focuses on the long-term capability of salt repositories and the associated geologic media to safely isolate stored radioactive waste from the surrounding environment, even in the event of a human intrusion scenario such as a direct brine release (DBR) due to a drilling operation intersecting a brine pocket. In particular, we are revisiting the degree of conservatism in the estimated sorption partition coefficients (Kds) used in the PA model based on complementary batch and column experimental methods (Dittrich and Reimus, 2016). The main focus of this work is to investigate the role of ionic strength, solution chemistry, and oxidation state (III-VI) in actinide sorption to dolomite rock. Based on redox conditions and solution chemistry expected in the WIPP, possible actinide species include Pu(III), Pu(IV), U(IV), U(VI), Np(IV), Np(V), Am(III), and Th(IV). We will present (1) a conceptual overview of Kd use in the PA model, (2) background and evolution of the Kd ranges used, and (3) results from batch and column experiments and model predictions for Kds with WIPP-relevant geologic media. We will also briefly discuss the challenges of upscaling from lab experiments to field scale predictions, the presence of ligands (e.g., acetate, citrate, EDTA), the role of colloids and microbes, and the effect of engineered barrier materials (e.g., MgO) on sorption and transport conditions. References: Dittrich, T.M., Reimus, P.W. 2016. Reactive transport of uranium in fractured crystalline rock: Upscaling in time and distance. J Environ Manage 165, 124-132.

Waste Isolation Pilot Plant (WIPP) fact sheet

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1993-10-01

Pursuant to the Solid Waste Disposal Act, as amended by the Resource Conservation and Recovery Act (RCRA), as amended (42 USC 6901, et seq.), and the New Mexico Hazardous Waste Act (Section 74-4-1 et seq., NMSA 1978), Permit is issued to the owner and operator of the US DOE, WIPP site (hereafter called the Permittee(s)) to operate a hazardous waste storage facility consisting of a container storage unit (Waste Handling Building) and two Subpart X miscellaneous below-ground storage units (Bin Scale Test Rooms 1 and 3), all are located at the above location. The Permittee must comply with all termsmore » and conditions of this Permit. This Permit consists of the conditions contained herein, including the attachments. Applicable regulations cited are the New Mexico Hazardous Waste Management Regulations, as amended 1992 (HWMR-7), the regulations that are in effect on the date of permit issuance. This Permit shall become effective upon issuance by the Secretary of the New Mexico Environment Department and shall be in effect for a period of ten (10) years from issuance. This Permit is also based on the assumption that all information contained in the Permit application and the administrative record is accurate and that the activity will be conducted as specified in the application and the administrative record. The Permit application consists of Revision 3, as well as associated attachments and clarifying information submitted on January 25, 1993, and May 17, 1993.« less

RH Packaging Program Guidance

DOE Office of Scientific and Technical Information (OSTI.GOV)

Washington TRU Solutions, LLC

The purpose of this program guidance document is to provide technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the SARP and/or C of C shall govern. The C of C states: ''...each package must be prepared for shipment and operated in accordance with themore » procedures described in Chapter 7.0, ''Operating Procedures,'' of the application.'' It further states: ''...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, ''Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC approved, users need to be familiar with 10 CFR {section} 71.11, ''Deliberate Misconduct.'' Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions. Following these instructions assures that operations are safe and meet the requirements of the SARP. This document is available on the Internet at: ttp://www.ws/library/t2omi/t2omi.htm. Users are responsible for ensuring they are using the current revision and change notices. Sites may prepare their own document using the word-for-word steps in th is document, in sequence, including Notes and cautions. Site specific information may be included as necessary. The document, and revisions, must then be submitted to CBFO at sitedocuments@wipp.ws for approval. A copy of the approval letter from CBFO shall be available for audit purposes. Users may develop site-specific procedures addressing preoperational activities, quality assurance (QA), hoisting and rigging, and radiation health physics to be used with the instructions contained in this document. Users may recommend changes to this document by submitting their recommendations (in writing) to the WIPP M&O Contractor RH Packaging Maintenance Engineer for evaluation. If approved, the change(s) will be incorporated into this document for use by ALL users. Before first use and every 12 months after, user sites will be audited to this document to ensure compliance. They will also be audited within one year from the effective date of revisions to this document.« less

WIPP Waste Information Systems (WWIS)

EPA Pesticide Factsheets

EPA approved the INL-CCP and ANL-CCP RH TRU WC programs based on a demonstration of the sites’ capabilities, with conditions and limitations as documented in the INL Baseline Final Inspection Report and the ANL Baseline Final Inspection Report.

Issues in establishing an aerosol radiological baseline for the waste isolation pilot plant near Carlsbad, New Mexico.

PubMed

Rodgers, J C; Kenney, J W

1997-02-01

The Department of Energy has constructed a deep geologic repository for defense transuranic waste disposal. The Waste Isolation Pilot Plant, located in Southeastern New Mexico, is slated to receive transuranic waste by truck delivery beginning in 1998. The Environmental Evaluation Group (EEG) provides an independent evaluation of the impact on the health and environment in New Mexico of the WIPP project. Since 1985, the EEG has operated a network of air monitoring sites around WIPP and in nearby communities. The radionuclide concentration data from these air samples have been assembled into a useful baseline data base after resolution of a number of methodological and quality assurance issues. Investigation thresholds for the principal radionuclides have been calculated from combined data collected from several sites. These action levels will provide a critical quantitative basis for decisions of whether future airborne radionuclide measurements are attributable to accidental releases.

Final voluntary release assessment/corrective action report

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1996-11-12

The US Department of Energy, Carlsbad Area Office (DOE-CAO) has completed a voluntary release assessment sampling program at selected Solid Waste Management Units (SWMUs) at the Waste Isolation Pilot Plant (WIPP). This Voluntary Release Assessment/Corrective Action (RA/CA) report has been prepared for final submittal to the Environmental protection Agency (EPA) Region 6, Hazardous Waste Management Division and the New Mexico Environment Department (NMED) Hazardous and Radioactive Materials Bureau to describe the results of voluntary release assessment sampling and proposed corrective actions at the SWMU sites. The Voluntary RA/CA Program is intended to be the first phase in implementing the Resourcemore » Conservation and Recovery Act (RCRA) Facility Investigation (RFI) and corrective action process at the WIPP. Data generated as part of this sampling program are intended to update the RCRA Facility Assessment (RFA) for the WIPP (Assessment of Solid Waste Management Units at the Waste Isolation Pilot Plant), NMED/DOE/AIP 94/1. This Final Voluntary RA/CA Report documents the results of release assessment sampling at 11 SWMUs identified in the RFA. With this submittal, DOE formally requests a No Further Action determination for these SWMUs. Additionally, this report provides information to support DOE`s request for No Further Action at the Brinderson and Construction landfill SWMUs, and to support DOE`s request for approval of proposed corrective actions at three other SWMUs (the Badger Unit Drill Pad, the Cotton Baby Drill Pad, and the DOE-1 Drill Pad). This information is provided to document the results of the Voluntary RA/CA activities submitted to the EPA and NMED in August 1995.« less

Development of consistent hazard controls for DOE transuranic waste operations

DOE Office of Scientific and Technical Information (OSTI.GOV)

Woody, W.J.

2007-07-01

This paper describes the results of a re-engineering initiative undertaken with the Department of Energy's (DOE) Office of Environmental Management (EM) in order to standardize hazard analysis assumptions and methods and resulting safety controls applied to multiple transuranic (TRU) waste operations located across the United States. A wide range of safety controls are historically applied to transuranic waste operations, in spite of the fact that these operations have similar operational characteristics and hazard/accident potential. The re-engineering effort supported the development of a DOE technical standard with specific safety controls designated for accidents postulated during waste container retrieval, staging/storage, venting, onsitemore » movements, and characterization activities. Controls cover preventive and mitigative measures; include both hardware and specific administrative controls; and provide protection to the facility worker, onsite co-located workers and the general public located outside of facility boundaries. The Standard development involved participation from all major DOE sites conducting TRU waste operations. Both safety analysts and operations personnel contributed to the re-engineering effort. Acknowledgment is given in particular to the following individuals who formed a core working group: Brenda Hawks, (DOE Oak Ridge Office), Patrice McEahern (CWI-Idaho), Jofu Mishima (Consultant), Louis Restrepo (Omicron), Jay Mullis (DOE-ORO), Mike Hitchler (WSMS), John Menna (WSMS), Jackie East (WSMS), Terry Foppe (CTAC), Carla Mewhinney (WIPP-SNL), Stephie Jennings (WIPP-LANL), Michael Mikolanis (DOESRS), Kraig Wendt (BBWI-Idaho), Lee Roberts (Fluor Hanford), and Jim Blankenhorn (WSRC). Additional acknowledgment is given to Dae Chung (EM) and Ines Triay (EM) for leadership and management of the re-engineering effort. (authors)« less

Roadmap for disposal of Electrorefiner Salt as Transuranic Waste.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Rechard, Robert P.; Trone, Janis R.; Kalinina, Elena Arkadievna

The experimental breeder reactor (EBR-II) used fuel with a layer of sodium surrounding the uranium-zirconium fuel to improve heat transfer. Disposing of EBR-II fuel in a geologic repository without treatment is not prudent because of the potentially energetic reaction of the sodium with water. In 2000, the US Department of Energy (DOE) decided to treat the sodium-bonded fuel with an electrorefiner (ER), which produces metallic uranium product, a metallic waste, mostly from the cladding, and the salt waste in the ER, which contains most of the actinides and fission products. Two waste forms were proposed for disposal in a minedmore » repository; the metallic waste, which was to be cast into ingots, and the ER salt waste, which was to be further treated to produce a ceramic waste form. However, alternative disposal pathways for metallic and salt waste streams may reduce the complexity. For example, performance assessments show that geologic repositories can easily accommodate the ER salt waste without treating it to form a ceramic waste form. Because EBR-II was used for atomic energy defense activities, the treated waste likely meets the definition of transuranic waste. Hence, disposal at the Waste Isolation Pilot Plant (WIPP) in southern New Mexico, may be feasible. This report reviews the direct disposal pathway for ER salt waste and describes eleven tasks necessary for implementing disposal at WIPP, provided space is available, DOE decides to use this alternative disposal pathway in an updated environmental impact statement, and the State of New Mexico grants permission.« less

The Advancement of Public Awareness, Concerning TRU Waste Characterization, Using a Virtual Document

DOE Office of Scientific and Technical Information (OSTI.GOV)

West, T. B.; Burns, T. P.; Estill, W. G.

2002-02-28

Building public trust and confidence through openness is a goal of the DOE Carlsbad Field Office for the Waste Isolation Pilot Plant (WIPP). The objective of the virtual document described in this paper is to give the public an overview of the waste characterization steps, an understanding of how waste characterization instrumentation works, and the type and amount of data generated from a batch of drums. The document is intended to be published on a web page and/or distributed at public meetings on CDs. Users may gain as much information as they desire regarding the transuranic (TRU) waste characterization program,more » starting at the highest level requirements (drivers) and progressing to more and more detail regarding how the requirements are met. Included are links to: drivers (which include laws, permits and DOE Orders); various characterization steps required for transportation and disposal under WIPP's Hazardous Waste Facility Permit; physical/chemical basis for each characterization method; types of data produced; and quality assurance process that accompanies each measurement. Examples of each type of characterization method in use across the DOE complex are included. The original skeleton of the document was constructed in a PowerPoint presentation and included descriptions of each section of the waste characterization program. This original document had a brief overview of Acceptable Knowledge, Non-Destructive Examination, Non-Destructive Assay, Small Quantity sites, and the National Certification Team. A student intern was assigned the project of converting the document to a virtual format and to discuss each subject in depth. The resulting product is a fully functional virtual document that works in a web browser and functions like a web page. All documents that were referenced, linked to, or associated, are included on the virtual document's CD. WIPP has been engaged in a variety of Hazardous Waste Facility Permit modification activities. During the public meetings, discussion centered on proposed changes to the characterization program. The philosophy behind the virtual document is to show the characterization process as a whole, rather than as isolated parts. In addition to public meetings, other uses for the information might be as a training tool for new employees at the WIPP facility to show them where their activities fit into the overall scheme, as well as an employee review to help prepare for waste certification audits.« less

EPA's Review of DOE's Inventory Tracking for TRU Wastes at Waste Control Specialists

EPA Pesticide Factsheets

On April 9, 2014, EPA's Waste Isolation Pilot Plant (WIPP) waste characterization team visited Waste Control Specialists (WCS) to determine whether DOE was meeting EPA's waste inventory tracking requirements at 40 CFR 194.24(c)(4).

DOE Office of Scientific and Technical Information (OSTI.GOV)

Weaver, Brian Phillip

The purpose of this document is to describe the statistical modeling effort for gas concentrations in WIPP storage containers. The concentration (in ppm) of CO 2 in the headspace volume of standard waste box (SWB) 68685 is shown. A Bayesian approach and an adaptive Metropolis-Hastings algorithm were used.

Experimental Work Conducted on MgO Inundated Hydration in WIPP-Relevant Brines

NASA Astrophysics Data System (ADS)

Deng, H.; Xiong, Y.; Nemer, M. B.; Johnsen, S.

2009-12-01

Magnesium oxide (MgO) is being emplaced in the Waste Isolation Pilot Plant (WIPP) as an engineered barrier to mitigate the effect of microbial CO2 generation on actinide mobility in a postclosure repository environment. MgO will sequester CO2 and consume water in brine or water vapor in the gaseous phase. Martin Marietta (MM) MgO is currently being emplaced in the WIPP. A fractional-factorial experiment has been performed to study the inundated-hydration of MM MgO as a function of its particle size, solid-to-liquid ratio, and brine type. MgO hydration experiments have been carried out with three MgO particle sizes and two solid-to-liquid ratios in three WIPP-related brines: ERDA-6, GWB and simplified GWB. ERDA-6 is a synthetic NaCl-rich brine typical of a Castile brine reservoir below the repository. GWB is a synthetic MgCl2- and NaCl-rich brine representative of intergranular brines from the Salado Formation at or near the stratigraphic horizon of the repository. Simplified GWB contains amounts of Mg, Na, and Cl similar to those in GWB without other minor constituents. The hydration products include brucite (Mg(OH)2) and phase 5 (Mg3(OH)5Cl4H2O). In addition to phase 5, MgO hydration in GWB or simplified GWB produces brucite, whereas MgO hydrated in ERDA-6 only produces brucite. The MgO particle size has had a significant effect on the formation of hydration products: small MgO particles have hydrated before the large particles. MgO has hydrated faster in simplified GWB than in the other two brines. In ERDA-6, the solid-to-liquid ratio has affected the brine pH due to the presence of CaO (~1 wt %) as an impurity in MM MgO. GWB has sufficient dissolved Mg to buffer pH despite small amounts of CaO. Both our results and thermodynamic modeling indicate that phase-5 is the stable Mg-OH-Cl phase in Mg-Na-Cl-dominated brines with ionic strengths and chemical compositions similar to that of GWB. In contrast, phase-3 (Mg2(OH)3Cl4H2O) is the stable phase in the MgCl2-saturated Q-brine, a high-ionic-strength (up to 15 m) brine from Asse, Germany. We used EQ3/6 to simulate MgO hydration and carbonation in a closed system containing brine and CO2 at atmospheric concentration by titrating periclase into the system. (EQ3/6 is a geochemical software package for speciation, solubility calculations and reaction path modeling.) EQ3/6 predicted Mg and Cl concentrations and pH similar to the experimentally observed values. EQ3/6 also predicted hydration products similar to thsoe observed experimentally. * This research is funded by WIPP programs administered by the U.S. Department of Energy. ** Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy’s National Nuclear Security Administration under contract DE-AC04-94AL85000.

No-migration variance petition. Appendices K--O, Response to notice of deficiencies: Volume 6, Revision 1

DOE Office of Scientific and Technical Information (OSTI.GOV)

Fischer, N.T.

1990-03-01

This document reports data collected as part of the Ecological Monitoring Program (EMP) at the Waste Isolation Pilot Plant near Carlsbad, New Mexico, for Calendar Year 1987. Also included are data from the last quarter (October through December) of 1986. This report divides data collection activities into two parts. Part A covers general environmental monitoring which includes meteorology, aerial photography, air quality monitoring, water quality monitoring, and wildlife population surveillance. Part B focuses on the special studies being performed to evaluate the impacts of salt dispersal from the site on the surrounding ecosystem. The fourth year of salt impact monitoringmore » was completed in 1987. These studies involve the monitoring of soil chemistry, soil microbiota, and vegetation in permanent study plots. None of the findings indicate that the WIPP project is adversely impacting environmental quality at the site. As in 1986, breeding bird censuses completed this year indicate changes in the local bird fauna associated with the WIPP site. The decline in small mammal populations noted in the 1986 census is still evident in the 1987 data; however, populations are showing signs of recovery. There is no indication that this decline is related to WIPP activities. Rather, the evidence indicates that natural population fluctuations may be common in this ecosystem. The salt impact studies continue to reveal some short-range transport of salt dust from the saltpiles. This material accumulates at or near the soil surface during the dry seasons in areas near the saltpiles, but is flushed deeper into the soil during the rainy season. Microbial activity does not appear to be affected by this salt importation. Vegetation coverage and density data from 1987 also do not show any detrimental effect associated with aerial dispersal of salt.« less

Defense Remote Handled Transuranic Waste Cost/Schedule Optimization Study

DOE Office of Scientific and Technical Information (OSTI.GOV)

Pierce, G.D.; Beaulieu, D.H.; Wolaver, R.W.

1986-11-01

The purpose of this study is to provide the DOE information with which it can establish the most efficient program for the long management and disposal, in the Waste Isolation Pilot Plant (WIPP), of remote handled (RH) transuranic (TRU) waste. To fulfill this purpose, a comprehensive review of waste characteristics, existing and projected waste inventories, processing and transportation options, and WIPP requirements was made. Cost differences between waste management alternatives were analyzed and compared to an established baseline. The result of this study is an information package that DOE can use as the basis for policy decisions. As part ofmore » this study, a comprehensive list of alternatives for each element of the baseline was developed and reviewed with the sites. The principle conclusions of the study follow. A single processing facility for RH TRU waste is both necessary and sufficient. The RH TRU processing facility should be located at Oak Ridge National Laboratory (ORNL). Shielding of RH TRU to contact handled levels is not an economic alternative in general, but is an acceptable alternative for specific waste streams. Compaction is only cost effective at the ORNL processing facility, with a possible exception at Hanford for small compaction of paint cans of newly generated glovebox waste. It is more cost effective to ship certified waste to WIPP in 55-gal drums than in canisters, assuming a suitable drum cask becomes available. Some waste forms cannot be packaged in drums, a canister/shielded cask capability is also required. To achieve the desired disposal rate, the ORNL processing facility must be operational by 1996. Implementing the conclusions of this study can save approximately $110 million, compared to the baseline, in facility, transportation, and interim storage costs through the year 2013. 10 figs., 28 tabs.« less

40 CFR 194.24 - Waste characterization.

Code of Federal Regulations, 2010 CFR

2010-07-01

... other information and methods. (b) The Department shall submit in the compliance certification... proposed for disposal in the disposal system, WIPP complies with the numeric requirements of § 194.34 and... release. (2) Identify and describe the method(s) used to quantify the limits of waste components...

Options Assessment Report: Treatment of Nitrate Salt Waste at Los Alamos National Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

Robinson, Bruce Alan; Stevens, Patrice Ann

2015-12-17

This report documents the methodology used to select a method of treatment for the remediated nitrate salt (RNS) and unremediated nitrate salt (UNS) waste containers at Los Alamos National Laboratory (LANL). The method selected should treat the containerized waste in a manner that renders the waste safe and suitable for transport and final disposal in the Waste Isolation Pilot Plant (WIPP) repository, under specifications listed in the WIPP Waste Acceptance Criteria (DOE/CBFO, 2013). LANL recognizes that the results must be thoroughly vetted with the New Mexico Environment Department (NMED) and that a modification to the LANL Hazardous Waste Facility Permitmore » is a necessary step before implementation of this or any treatment option. Likewise, facility readiness and safety basis approvals must be received from the Department of Energy (DOE). This report presents LANL’s preferred option, and the documentation of the process for reaching the recommended treatment option for RNS and UNS waste, and is presented for consideration by NMED and DOE.« less

Waste Isolation Pilot Plant Site Environmental Report for 1998

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hooda, Balwan S.; Allen, Vivian L.

This 1998 annual Site Environmental Report (SER) was prepared in accordance with U.S. Department of Energy (DOE) Order 5400.1, ''General Environmental Protection Program''; DOE Order 231.1, ''Environmental Safety and Health Reporting''; the ''Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance'' (DOE/EH-0173T); and the Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an SER to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of the SER is to provide a comprehensive description of operational environmental monitoring activities, an abstract of environmental activities conducted tomore » characterize site environmental management performance, to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during calendar year ( CY) 1998. The content of this SER is not restricted to a synopsis of the required data. Information pertaining to new and continued monitoring and compliance activities during CY 1998 are also included.« less

Potash ore reserves in the proposed Waste Isolation Pilot Plant area, Eddy County, southeastern New Mexico

USGS Publications Warehouse

John, Charles B.; Cheeseman, R.J.; Lorenz, J.C.; Millgate, M.L.

1978-01-01

The proposed Waste Isolation Pilot Plant (WIPP) area includes about 18,960 acres in Tps. 22 and 23 S., Rs. 30 and 31 E., New Mexico Principal Meridian, Eddy County, southeastern New Mexico. It is located within the Carlsbad Mining District about 25 miles east of Carlsbad. The WIPP area is immediately south of the Capitan Limestone subcrop, which formed the northern margin of the Delaware basin in Permian time. During Late Permian (Ochoan) time, gypsum, anhydrite, and halite were deposited in the seas of the Delaware basin to form the Castile Formation. These deposits have a maximum thickness of about 2,000 feet and grade upward into the more argillaceous beds of the Salado Formation. The Salado Formation contains abundant sulfate minerals, notably anhydrite and polyhalite. The potash ore minerals, langbeinite and sylvite, occur in the upper part of the Salado Formation in the McNutt potash zone, a local name applied to a potassium-rich zone.

CsIX/TRU Grout Feasibility Study

DOE Office of Scientific and Technical Information (OSTI.GOV)

S. J. Losinski; C. M. Barnes; B. K. Grover

A settlement agreement between the Department of Energy (DOE) and the State of Idaho mandates that liquid waste now stored at the Idaho Nuclear Technology Engineering Center (INTEC - formerly the Idaho Chemical Processing Plant, ICPP) will be calcined by the end of year 2012. This study investigates an alternative treatment of the liquid waste that removes undissolved solids (UDS) by filtration and removes cesium by ion exchange followed by cement-based grouting of the remaining liquid into 55-gal drums. Operations are assumed to be from January 2008 through December 2012. The grouted waste will be contact-handled and will be shippedmore » to the Waste Isolation Pilot Plant (WIPP) in New Mexico for disposal. The small volume of secondary wastes such as the filtered solids and cesium sorbent (resin) would remain in storage at the Idaho National Engineering and Environmental Laboratory for treatment and disposal under another project, with an option to dispose of the filtered solids as a r emote-handled waste at WIPP.« less

Final Inventory Work-Off Plan for ORNL transuranic wastes (1986 version)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Dickerson, L.S.

1988-05-01

The Final Inventory Work-Off Plan (IWOP) for ORNL Transuranic Wastes addresses ORNL's strategy for retrieval, certification, and shipment of its stored and newly generated contact-handled (CH) and remote-handled (RH) transuranic (TRU) wastes to the Waste Isolation Pilot Plant (WIPP), the proposed geologic repository near Carlsbad, New Mexico. This document considers certification compliance with the WIPP waste acceptance criteria (WAC) and is consistent with the US Department of Energy's Long-Range Master Plan for Defense Transuranic Waste Management. This document characterizes Oak Ridge National Laboratory's (ORNL's) TRU waste by type and estimates the number of shipments required to dispose of it; describesmore » the methods, facilities, and systems required for its certification and shipment; presents work-off strategies and schedules for retrieval, certification, and transportation; discusses the resource needs and additions that will be required for the effort and forecasts costs for the long-term TRU waste management program; and lists public documentation required to support certification facilities and strategies. 22 refs., 6 figs., 10 tabs.« less

Milestones for disposal of radioactive waste at the Waste Isolation Pilot Plant (WIPP) in the United States

DOE Office of Scientific and Technical Information (OSTI.GOV)

RECHARD,ROBERT P.

The opening of the Waste Isolation Pilot Plant on March 26, 1999, was the culmination of a regulatory assessment process that had taken 25 years. National policy issues, negotiated agreements, and court settlements during the first 15 years of the project had a strong influence on the amount and type of scientific data collected up to this point. Assessment activities before the mid 1980s were undertaken primarily (1) to satisfy needs for environmental impact statements, (2) to satisfy negotiated agreements with the State of New Mexico, or (3) to develop general understanding of selected natural phenomena associated with nuclear wastemore » disposal. In the last 10 years, federal compliance policy and actual regulations were sketched out, and continued to evolve until 1996. During this period, stochastic simulations were introduced as a tool for the assessment of the WIPP's performance, and four preliminary performance assessments, one compliance performance assessment, and one verification performance assessment were performed.« less

Remote Handled WIPP Canisters at Los Alamos National Laboratory Characterized for Retrieval

DOE Office of Scientific and Technical Information (OSTI.GOV)

Griffin, J.; Gonzales, W.

2007-07-01

The Los Alamos National Laboratory (LANL) is pursuing retrieval, transportation, and disposal of 16 remote handled transuranic waste canisters stored below ground in shafts since 1994. These canisters were retrievably stored in the shafts to await Nuclear Regulatory Commission certification of the Model Number RH-TRU 72B transportation cask and authorization of the Waste Isolation Pilot Plant (WIPP) to accept the canisters for disposal. Retrieval planning included radiological characterization and visual inspection of the canisters to confirm historical records, verify container integrity, determine proper personnel protection for the retrieval operations, provide radiological dose and exposure rate data for retrieval operations, andmore » to provide exterior radiological contamination data. The radiological characterization and visual inspection of the canisters was performed in May 2006. The effort required the development of remote techniques and equipment due to the potential for personnel exposure to radiological doses approaching 300 R/hr. Innovations included the use of two nested 1.5 meter (m) (5-feet [ft]) long concrete culvert pipes (1.1-m [42 inch (in.)] and 1.5-m [60-in] diameter, respectively) as radiological shielding and collapsible electrostatic dusting wands to collect radiological swipe samples from the annular space between the canister and shaft wall. Visual inspection indicated that the canisters are in good condition with little or no rust, the welded seams are intact, and ten of the canisters include hydrogen gas sampling equipment on the pintle that will have to be removed prior to retrieval. The visual inspection also provided six canister identification numbers that matched historical storage records. The exterior radiological data indicated alpha and beta contamination below LANL release criteria and radiological dose and exposure rates lower than expected based upon historical data and modeling of the canister contents. (authors)« less

Simultaneous Thermal Analysis of WIPP and LANL Waste Drum Samples: A Preliminary Report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Wayne, David M.

2015-10-19

On Friday, February 14, 2014, an incident in P7R7 of the WIPP underground repository released radioactive material into the environment. The direct cause of the event was a breached transuranic (TRU) waste container, subsequently identified as Drum 68660. Photographic and other evidence indicates that the breach of 68660 was caused by an exothermic event. Subsequent investigations (Britt, 2015; Clark and Funk, 2015; Wilson et al., 2015; Clark, 2015) indicate that the combination of nitrate salts, pH neutralizing chemicals, and organic-based adsorbent represented a potentially energetic mixture. The materials inside the breached steel drum consisted of remediated, 30- to 40-year old,more » Pu processing wastes from LANL. The contents were processed and repackaged in 2014. Processing activities at LANL included: 1) neutralization of acidic liquid contents, 2) sorption of the neutralized liquid, and 3) mixing of acidic nitrate salts with an absorber to meet waste acceptance criteria. The contents of 68660 and its sibling, 68685, were derived from the same parent drum, S855793. Drum S855793 originally contained ten plastic bags of acidic nitrate salts, and four bags of mixed nitrate and oxalate salts generated in 1985 by Pu recovery operations. These salts were predominantly oxalic acid, hydrated nitrate salts of Mg, Ca, and Fe, anhydrous Na(NO 3), and minor amounts of anhydrous and hydrous nitrate salts of Pb, Al, K, Cr, and Ni. Other major components include sorbed water, nitric acid, dissolved nitrates, an absorbent (Swheat Scoop®) and a neutralizer (KolorSafe®). The contents of 68660 are described in greater detail in Appendix E of Wilson et al. (2015)« less

Condensed listing of surface boreholes at the Waste Isolation Pilot Plant Project through 31 December 1995

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hill, L.R.; Aguilar, R.; Mercer, J.W.

This report contains a condensed listing of Waste Isolation Pilot Plant (WIPP) project surface boreholes drilled for the purpose of site selection and characterization through 31 December 1995. The US Department of Energy (DOE) sponsored the drilling activities, which were conducted primarily by Sandia National Laboratories. The listing provides physical attributes such as location (township, range, section, and state-plane coordinates), elevation, and total borehole depth, as well as the purpose for the borehole, drilling dates, and information about extracted cores. The report also presents the hole status (plugged, testing, monitoring, etc.) and includes salient findings and references. Maps with boreholemore » locations and times-of-drilling charts are included.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Jensen, A.L.; Howard, C.L.; Jones, R.L.

Pore-pressure and fluid-flow tests were performed in 15 boreholes drilled into the bedded evaporites of the Salado Formation from within the Waste Isolation Pilot Plant (WIPP). The tests measured fluid flow and pore pressure within the Salado. The boreholes were drilled into the previously undisturbed host rock around a proposed cylindrical test room, Room Q, located on the west side of the facility about 655 m below ground surface. The boreholes were about 23 m deep and ranged over 27.5 m of stratigraphy. They were completed and instrumented before excavation of Room Q. Tests were conducted in isolated zones atmore » the end of each borehole. Three groups of 5 isolated zones extend above, below, and to the north of Room Q at increasing distances from the room axis. Measurements recorded before, during, and after the mining of the circular test room provided data about borehole closure, pressure, temperature, and brine seepage into the isolated zones. The effects of the circular excavation were recorded. This data report presents the data collected from the borehole test zones between April 25, 1989 and November 25, 1991. The report also describes test development, test equipment, and borehole drilling operations.« less

Enclosure from DOE letter dated 7/20/07 - Table 5-2, Isotopic Compositions of Rocky Flats Plutonium and Uranium

EPA Pesticide Factsheets

This enclosure from a DOE letter to EPA regarding a waste container disposed at the WIPP from the Advanced Mixed Waste Treatment Project includes Table 5-2, Isotopic Compositions of Rocky Flats Plutonium and Uranium.

40 CFR 194.2 - Definitions.

Code of Federal Regulations, 2013 CFR

2013-07-01

... pursuant to section 213 of the Department of Energy National Security and Military Applications of Nuclear.... Department means the United States Department of Energy. Disposal regulations means part 191, subparts B and... section 8(d)(1) of the WIPP LWA. Secretary means the Secretary of Energy. Shallow drilling means those...

40 CFR 194.2 - Definitions.

Code of Federal Regulations, 2014 CFR

2014-07-01

... pursuant to section 213 of the Department of Energy National Security and Military Applications of Nuclear.... Department means the United States Department of Energy. Disposal regulations means part 191, subparts B and... section 8(d)(1) of the WIPP LWA. Secretary means the Secretary of Energy. Shallow drilling means those...

40 CFR 194.2 - Definitions.

Code of Federal Regulations, 2012 CFR

2012-07-01

... pursuant to section 213 of the Department of Energy National Security and Military Applications of Nuclear.... Department means the United States Department of Energy. Disposal regulations means part 191, subparts B and... section 8(d)(1) of the WIPP LWA. Secretary means the Secretary of Energy. Shallow drilling means those...

40 CFR 194.2 - Definitions.

Code of Federal Regulations, 2010 CFR

2010-07-01

... pursuant to section 213 of the Department of Energy National Security and Military Applications of Nuclear.... Department means the United States Department of Energy. Disposal regulations means part 191, subparts B and... section 8(d)(1) of the WIPP LWA. Secretary means the Secretary of Energy. Shallow drilling means those...

40 CFR 194.2 - Definitions.

Code of Federal Regulations, 2011 CFR

2011-07-01

... pursuant to section 213 of the Department of Energy National Security and Military Applications of Nuclear.... Department means the United States Department of Energy. Disposal regulations means part 191, subparts B and... section 8(d)(1) of the WIPP LWA. Secretary means the Secretary of Energy. Shallow drilling means those...

Actinide Sorption in a Brine/Dolomite Rock System: Evaluating the Degree of Conservatism in Kd Ranges used in Performance Assessment Modeling for the WIPP Nuclear Waste Repository

NASA Astrophysics Data System (ADS)

Dittrich, T. M.; Reed, D. T.

2015-12-01

The Waste Isolation Pilot Plant (WIPP) near Carlsbad, NM is the only operating nuclear waste repository in the US and has been accepting transuranic (TRU) waste since 1999. The WIPP is located in a salt deposit approximately 650 m below the surface and performance assessment (PA) modeling for a 10,000 year period is required to recertify the operating license with the US EPA every five years. The main pathway of concern for environmental release of radioactivity is a human intrusion caused by drilling into a pressurized brine reservoir below the repository. This could result in the flooding of the repository and subsequent transport in the high transmissivity layer (dolomite-rich Culebra formation) above the waste disposal rooms. We evaluate the degree of conservatism in the estimated sorption partition coefficients (Kds) ranges used in the PA based on an approach developed with granite rock and actinides (Dittrich and Reimus, 2015; Dittrich et al., 2015). Sorption onto the waste storage material (Fe drums) may also play a role in mobile actinide concentrations. We will present (1) a conceptual overview of how Kds are used in the PA model, (2) technical background of the evolution of the ranges and (3) results from batch and column experiments and model predictions for Kds with WIPP dolomite and clays, brine with various actinides, and ligands (e.g., acetate, citrate, EDTA) that could promote transport. The current Kd ranges used in performance models are based on oxidation state and are 5-400, 0.5-10,000, 0.03-200, and 0.03-20 mL g-1 for elements with oxidation states of III, IV, V, and VI, respectively. Based on redox conditions predicted in the brines, possible actinide species include Pu(III), Pu(IV), U(IV), U(VI), Np(IV), Np(V), Am(III), and Th(IV). We will also discuss the challenges of upscaling from lab experiments to field scale predictions, the role of colloids, and the effect of engineered barrier materials (e.g., MgO) on transport conditions. Dittrich, T.M., Reimus, P.W. 2015. Uranium transport in a crushed granodiorite: experiments and reactive transport modeling. J Contam Hydrol 175-176: 44-59. Dittrich, T.M., Boukhalfa, H., Ware, S.D., Reimus, P.W. 2015. Laboratory investigation of the role of desorption kinetics on americium transport associated with bentonite colloids. J Environ Radioactiv 148: 170-182.

Complications Associated with Long-Term Disposition of Newly-Generated Transuranic Waste: A National Laboratory Perspective

DOE Office of Scientific and Technical Information (OSTI.GOV)

B.J. Orchard; L.A. Harvego; T.L. Carlson

The Idaho National Laboratory (INL) is a multipurpose national laboratory delivering specialized science and engineering solutions for the U.S. Department of Energy (DOE). Sponsorship of INL was formally transferred to the DOE Office of Nuclear Energy, Science and Technology (NE) by Secretary Spencer Abraham in July 2002. The move to NE, and designation as the DOE lead nuclear energy laboratory for reactor technology, supports the nation’s expanding nuclear energy initiatives, placing INL at the center of work to develop advanced Generation IV nuclear energy systems; nuclear energy/hydrogen coproduction technology; advanced nuclear energy fuel cycle technologies; and providing national security answersmore » to national infrastructure needs. As a result of the Laboratory’s NE mission, INL generates both contact-handled and remote-handled transuranic (TRU) waste from ongoing operations. Generation rates are relatively small and fluctuate based on specific programs and project activities being conducted; however, the Laboratory will continue to generate TRU waste well into the future in association with the NE mission. Currently, plans and capabilities are being established to transfer INL’s contact-handled TRU waste to the Advanced Mixed Waste Treatment Plant (AMWTP) for certification and disposal to the Waste Isolation Pilot Plant (WIPP). Remote-handled TRU waste is currently placed in storage at the Materials and Fuels Complex (MFC). In an effort to minimize future liabilities associated with the INL NE mission, INL is evaluating and assessing options for the management and disposition of all its TRU waste on a real-time basis at time of generation. This paper summarizes near-term activities to minimize future re handling of INL’s TRU waste, as well as, potential complications associated with the long-term disposition of newly-generated TRU waste. Potential complications impacting the disposition of INL newly-generated TRU waste include, but are not limited to: 1) required remote-handled TRU packaging configuration(s) vs. current facility capabilities, 2) long-term NE mission activities, 3) WIPP certification requirements, and 4) budget considerations.« less

Archaeological Investigations of Three Sites within the Wipp Core Area, Eddy County, New Mexico.

DTIC Science & Technology

1985-06-01

soils occasionally contain small playas, which hold water, generally quite saline , for short periods of time. Soils of this association are used for...be substituted for rhubarb (Castetter 1935:50). Portulacaceae Po 1*Maca. gZr Small purslane .E. Le Retose purslane Portulaca is a very important

Evaluation of the U.S. Environmental Protection Agency's Public Outreach Program during the Certification Process at the Waste Isolation Pilot Plant in New Mexico

EPA Pesticide Factsheets

The EPA Office of Radiation and Indoor Air (ORIA) contracted with Phoenix Environmental and EnviroIssues to evaluate the effectiveness of its public outreach program during its certification of the Waste Isolation Pilot Plant (WIPP) in Carlsbad, NM.

No-migration variance petition. Appendices C--J: Volume 5, Revision 1

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1990-03-01

Volume V contains the appendices for: closure and post-closure plans; RCRA ground water monitoring waver; Waste Isolation Division Quality Program Manual; water quality sampling plan; WIPP Environmental Procedures Manual; sample handling and laboratory procedures; data analysis; and Annual Site Environmental Monitoring Report for the Waste Isolation Pilot Plant.

Waste Isolation Pilot Plant Technical Assessment Team Report

DOE Office of Scientific and Technical Information (OSTI.GOV)

None, None

This report provides the results of the Waste Isolation Pilot Plant (WIPP) technical assessment led by the Savannah River National Laboratory and conducted by a team of experts in pertinent disciplines from SRNL and Lawrence Livermore National Laboratory (LLNL), Oak Ridge National Laboratory (ORNL), Pacific Northwest National Laboratory (PNNL), and Sandia National Laboratories (SNL).

Sodium Bearing Waste Processing Alternatives Analysis

DOE Office of Scientific and Technical Information (OSTI.GOV)

Murphy, James Anthony; Palmer, Brent J; Perry, Keith Joseph

2003-12-01

A multidisciplinary team gathered to develop a BBWI recommendation to DOE-ID on the processing alternatives for the sodium bearing waste in the INTEC Tank Farm. Numerous alternatives were analyzed using a rigorous, systematic approach. The data gathered were evaluated through internal and external peer reviews for consistency and validity. Three alternatives were identified to be top performers: Risk-based Calcination, MACT to WIPP Calcination and Cesium Ion Exchange. A dual-path through early Conceptual design is recommended for MACT to WIPP Calcination and Cesium Ion Exchange since Risk-based Calcination does not require design. If calcination alternatives are not considered based on givingmore » Type of Processing criteria significantly greater weight, the CsIX/TRUEX alternative follows CsIX in ranking. However, since CsIX/TRUEX shares common uncertainties with CsIX, reasonable backups, which follow in ranking, are the TRUEX and UNEX alternatives. Key uncertainties must be evaluated by the decision-makers to choose one final alternative. Those key uncertainties and a path forward for the technology roadmapping of these alternatives is provided.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Poppiti, James; Nelson, Roger; MacMillan, Walter J.

The Waste Isolation Pilot Plant (WIPP) is a 655-meter deep mine near Carlsbad, New Mexico, used to dispose the nation’s defense transuranic waste. Limited airborne radioactivity was released from a container of radioactive waste in WIPP on 14 February, 2014. As designed, a mine ventilation filtration system prevented the large scale release of contamination from the underground. However, isolation dampers leaked, which allowed the release of low levels of contaminants after the event until they were sealed. None of the exposed individuals received any recordable dose. While surface contamination was limited, contamination in the ventilation system and portions of themore » underground was substantial. High efficiency particulate air (HEPA) filters in the operating ventilation system ensure continued containment during recovery and resumption of disposal operations. However, ventilation flow is restricted since the incident, with all exhaust air directed through the filters. Decontamination and natural fixation by the hygroscopic nature of the salt host rock has reduced the likelihood of further contamination spread. Contamination control and ventilation system operability are crucial for resumption of operations. This article provides an operational assessment and evaluation of these two key areas.« less

Experiments and Modeling to Support Field Test Design

DOE Office of Scientific and Technical Information (OSTI.GOV)

Johnson, Peter Jacob; Bourret, Suzanne Michelle; Zyvoloski, George Anthony

Disposition of heat-generating nuclear waste (HGNW) remains a continuing technical and sociopolitical challenge. We define HGNW as the combination of both heat generating defense high level waste (DHLW) and civilian spent nuclear fuel (SNF). Numerous concepts for HGNW management have been proposed and examined internationally, including an extensive focus on geologic disposal (c.f. Brunnengräber et al., 2013). One type of proposed geologic material is salt, so chosen because of its viscoplastic deformation that causes self-repair of damage or deformation induced in the salt by waste emplacement activities (Hansen and Leigh, 2011). Salt as a repository material has been tested atmore » several sites around the world, notably the Morsleben facility in Germany (c.f. Fahland and Heusermann, 2013; Wollrath et al., 2014; Fahland et al., 2015) and at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, NM. Evaluating the technical feasibility of a HGNW repository in salt is an ongoing process involving experiments and numerical modeling of many processes at many facilities.« less

Thermal/structural modeling of a large scale in situ overtest experiment for defense high level waste at the Waste Isolation Pilot Plant Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Morgan, H.S.; Stone, C.M.; Krieg, R.D.

Several large scale in situ experiments in bedded salt formations are currently underway at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, USA. In these experiments, the thermal and creep responses of salt around several different underground room configurations are being measured. Data from the tests are to be compared to thermal and structural responses predicted in pretest reference calculations. The purpose of these comparisons is to evaluate computational models developed from laboratory data prior to fielding of the in situ experiments. In this paper, the computational models used in the pretest reference calculation for one of themore » large scale tests, The Overtest for Defense High Level Waste, are described; and the pretest computed thermal and structural responses are compared to early data from the experiment. The comparisons indicate that computed and measured temperatures for the test agree to within ten percent but that measured deformation rates are between two and three times greater than corresponsing computed rates. 10 figs., 3 tabs.« less

Deteriorated Concrete from Liner of WIPP Waste Shaft

DTIC Science & Technology

1992-06-01

for US Department of Energy. Bensted, J. 1989. "Novel Cements - Sorel and Related Chemical Cements," il Cemento , Vol 86, No. 4, pp 217-228. Ben-Yair, M...Waste Isolation Pilot Plant. Massazza, F. 1985. "Concrete Resistance to Sea Water and Marine Environment," il Cemento , Vol 82, No. 1, pp 3-26. Mather

DOE's Notification of Planned Change to the EPA 40 CFR Part 194 Certification of the Waste Isolation Pilot Plant: Remote-Handled Transuranic Waste Characterization Plan

EPA Pesticide Factsheets

The U.S. Department of Energy's Carlsbad Field Office (DOE/CBFO) provided the U.S. Environmental Protection Agency (EPA) this Notification of Planned Change to accept remote-handled (RH) transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP).

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hansen, Francis D.; Leigh, Christi; Stein, Walter

The 5th US/German Workshop on Salt Repository Research, Design, and Operation was held in Santa Fe New Mexico September 8-10, 2014. The forty seven registered participants were equally divided between the United States (US) and Germany, with one participant from The Netherlands. The agenda for the 2014 workshop was under development immediately upon finishing the 4th Workshop. Ongoing, fundamental topics such as thermomechanical behavior of salt, plugging and sealing, the safety case, and performance assessment continue to advance the basis for disposal of heat-generating nuclear waste in salt formations. The utility of a salt underground research laboratory (URL) remains anmore » intriguing concept engendering discussion of testing protocol. By far the most interest in this years’ workshop pertained to operational safety. Given events at the Waste Isolation Pilot Plant (WIPP), this discussion took on a new sense of relevance and urgency.« less

Pretest 3-D finite element modeling of the wedge pillar portion of the WIPP (Waste Isolation Pilot Plant) Geomechanical Evaluation (Room G) in situ experiment. [Waste Isolation Pilot Plant

DOE Office of Scientific and Technical Information (OSTI.GOV)

Preece, D.S.

Pretest 3-D finite element calculations have been performed on the wedge pillar portion of the WIPP Geomechanical Evaluation Experiment. The wedge pillar separates two drifts that intersect at an angle of 7.5/sup 0/. Purpose of the experiment is to provide data on the creep behavior of the wedge and progressive failure at the tip. The first set of calculations utilized a symmetry plane on the center-line of the wedge which allowed treatment of the entire configuration by modeling half of the geometry. Two 3-D calculations in this first set were performed with different drift widths to study the influence ofmore » drift size on closure and maximum stress. A cross-section perpendicular to the wedge was also analyzed with 2-D finite element models and the results compared to the 3-D results. In another set of 3-D calculations both drifts were modeled but with less distance between the drifts and the outer boundaries. Results of these calculations are compared with results from the other calculations to better understand the influence of boundary conditions.« less

Cf-252 Characterization Documents

DOE Office of Scientific and Technical Information (OSTI.GOV)

Feldman, Alexander

2014-03-14

Six documents were written by Vance and Associates under contract to the Off-Site Source Recovery Project of Los Alamos National Laboratory. These Six documents provided the basis for characterization of Californium-252 sealed sources and for the packaging and manifesting of this material for disposal at the Waste Isolation Pilot Project. The Six documents are: 1. VA-OSR-10, Development of radionuclide distributions for Cf-252 sealed sources. 2. VA-OSR-11, Uncertainty analysis for Cf-252 sealed sources. 3. VA-OSR-12, To determine the radionuclides in the waste drums containing Cf-252 sealed source waste that are required to be reported under the requirements of the WIPP WACmore » and the TRAMPAC. 4. VA-OSR-13, Development of the spreadsheet for the radiological calculations for the characterization of Cf-252 sources. 5. VA-OSR-14, Relative importance of neutron-induced fission in Cf-252 sources. 6. VA-OSR-15, Determine upper bound of decay product inventories from a drum of Cf-252 sources. These six documents provide the technical basis for the characterization of Cf-252 sources and will be part of the AK documentation required for submittal to the Central Characterization Project (CCP) of WIPP.« less

WIPP Hazardous Waste Facility Permit Update

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kehrman, B.; Most, W.

2006-07-01

The Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit (HWFP) was issued on October 27, 1999 [1]. Since that time, the WIPP has sought modifications to clarify the permit language, provide alternative methods for meeting permit requirements and to update permit conditions. Significant advancements have been made in transuranic (TRU) waste management as the result of modifications to the HWFP. Among these advancements is a modification to obtain a drum age criteria (DAC) value to perform headspace gas sampling on drums to be super-compacted and placed in a 100-gallon overpack drum. In addition, the Section 311 permit modification requestmore » that would allow for more efficient waste characterization, and the modification to authorize the shipment and disposal of Remote-Handled (RH) TRU waste were merged together and submitted to the regulator as the Consolidated Permit Modification Request (PMR). The submittal of the Consolidated PMR came at the request of the regulator as part of responses to Notices of Deficiency (NODs) for the separate PMRs which had been submitted in previous years. Section 311 of the fiscal year 2004 Energy and Water Developments Appropriations Act (Public Law 108-137) [2] directs the Department of Energy to submit a permit modification that limits waste confirmation to radiography or visual examination of a statistical subpopulation of containers. Section 311 also specifically directs that disposal room performance standards be to be met by monitoring for volatile organic compounds in the underground disposal rooms. This statute translates into the elimination of other waste confirmation methods such as headspace gas sampling and analysis and solids sampling and analysis. These methods, as appropriate, will continue to be used by the generator sites during hazardous waste determinations or characterization activities. This modification is expected to reduce the overall cost of waste analysis by hundreds of millions of dollars [3]. Combining both the chap. 311 and RH TRU waste permit modification requests allows for both the regulator and DOE to expedite action on the modification requests. The Combined PMR reduces costs by having only one administrative process for both modification requests. (authors)« less

Derivation of Pitzer Interaction Parameters for an Aqueous Species Pair of Sodium and Iron(II)-Citrate Complex

NASA Astrophysics Data System (ADS)

Jang, J. H.; Nemer, M.

2015-12-01

The U.S. DOE Waste Isolation Pilot Plant (WIPP) is a deep underground repository for the permanent disposal of transuranic (TRU) radioactive waste. The WIPP is located in the Permian Delaware Basin near Carlsbad, New Mexico, U.S.A. The TRU waste includes, but is not limited to, iron-based alloys and the complexing agent, citric acid. Iron is also present from the steel used in the waste containers. The objective of this analysis is to derive the Pitzer activity coefficients for the pair of Na+ and FeCit- complex to expand current WIPP thermodynamic database. An aqueous model for the dissolution of Fe(OH)2(s) in a Na3Cit solution was fitted to the experimentally measured solubility data. The aqueous model consists of several chemical reactions and related Pitzer interaction parameters. Specifically, Pitzer interaction parameters for the Na+ and FeCit- pair (β(0), β(1), and Cφ) plus the stability constant for species of FeCit- were fitted to the experimental data. Anoxic gloveboxes were used to keep the oxygen level low (<1 ppm) throughout the experiments due to redox sensitivity. EQ3NR, a computer program for geochemical aqueous speciation-solubility calculations, packaged in EQ3/6 v.8.0a, calculates the aqueous speciation and saturation index using an aqueous model addressed in EQ3/6's database. The saturation index indicates how far the system is from equilibrium with respect to the solid of interest. Thus, the smaller the sum of squared saturation indices that the aqueous model calculates for the given number of experiments, the more closely the model attributes equilibrium to each individual experiment with respect to the solid of interest. The calculation of aqueous speciation and saturation indices was repeated by adjusting stability constant of FeCit-, β(0), β(1), and Cφ in the database until the values are found that make the sum of squared saturation indices the smallest for the given number of experiments. Results will be presented at the time of conference.

Radiological Characterization Methodology of INEEL Stored RH-TRU Waste from ANL-E

DOE Office of Scientific and Technical Information (OSTI.GOV)

Rajiv N. Bhatt

2003-02-01

An Acceptable Knowledge (AK)-based radiological characterization methodology is being developed for RH TRU waste generated from ANL-E hot cell operations performed on fuel elements irradiated in the EBR-II reactor. The methodology relies on AK for composition of the fresh fuel elements, their irradiation history, and the waste generation and collection processes. Radiological characterization of the waste involves the estimates of the quantities of significant fission products and transuranic isotopes in the waste. Methods based on reactor and physics principles are used to achieve these estimates. Because of the availability of AK and the robustness of the calculation methods, the AK-basedmore » characterization methodology offers a superior alternative to traditional waste assay techniques. Using this methodology, it is shown that the radiological parameters of a test batch of ANL-E waste is well within the proposed WIPP Waste Acceptance Criteria limits.« less

Radiological Characterization Methodology for INEEL-Stored Remote-Handled Transuranic (RH TRU) Waste from Argonne National Laboratory-East

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kuan, P.; Bhatt, R.N.

2003-01-14

An Acceptable Knowledge (AK)-based radiological characterization methodology is being developed for RH TRU waste generated from ANL-E hot cell operations performed on fuel elements irradiated in the EBR-II reactor. The methodology relies on AK for composition of the fresh fuel elements, their irradiation history, and the waste generation and collection processes. Radiological characterization of the waste involves the estimates of the quantities of significant fission products and transuranic isotopes in the waste. Methods based on reactor and physics principles are used to achieve these estimates. Because of the availability of AK and the robustness of the calculation methods, the AK-basedmore » characterization methodology offers a superior alternative to traditional waste assay techniques. Using the methodology, it is shown that the radiological parameters of a test batch of ANL-E waste is well within the proposed WIPP Waste Acceptance Criteria limits.« less

Coupling of Nuclear Waste Form Corrosion and Radionuclide Transports in Presence of Relevant Repository Sediments

DOE Office of Scientific and Technical Information (OSTI.GOV)

Wall, Nathalie A.; Neeway, James J.; Qafoku, Nikolla P.

2015-09-30

Assessments of waste form and disposal options start with the degradation of the waste forms and consequent mobilization of radionuclides. Long-term static tests, single-pass flow-through tests, and the pressurized unsaturated flow test are often employed to study the durability of potential waste forms and to help create models that predict their durability throughout the lifespan of the disposal site. These tests involve the corrosion of the material in the presence of various leachants, with different experimental designs yielding desired information about the behavior of the material. Though these tests have proved instrumental in elucidating various mechanisms responsible for material corrosion,more » the chemical environment to which the material is subject is often not representative of a potential radioactive waste repository where factors such as pH and leachant composition will be controlled by the near-field environment. Near-field materials include, but are not limited to, the original engineered barriers, their resulting corrosion products, backfill materials, and the natural host rock. For an accurate performance assessment of a nuclear waste repository, realistic waste corrosion experimental data ought to be modeled to allow for a better understanding of waste form corrosion mechanisms and the effect of immediate geochemical environment on these mechanisms. Additionally, the migration of radionuclides in the resulting chemical environment during and after waste form corrosion must be quantified and mechanisms responsible for migrations understood. The goal of this research was to understand the mechanisms responsible for waste form corrosion in the presence of relevant repository sediments to allow for accurate radionuclide migration quantifications. The rationale for this work is that a better understanding of waste form corrosion in relevant systems will enable increased reliance on waste form performance in repository environments and potentially decrease the need for expensive engineered barriers.Our current work aims are 1) quantifying and understanding the processes associated with glass alteration in contact with Fe-bearing materials; 2) quantifying and understanding the processes associated with glass alteration in presence of MgO (example of engineered barrier used in WIPP); 3) identifying glass alteration suppressants and the processes involved to reach glass alteration suppression; 4) quantifying and understanding the processes associated with Saltstone and Cast Stone (SRS and Hanford cementitious waste forms) in various representative groundwaters; 5) investigating positron annihilation as a new tool for the study of glass alteration; and 6) quantifying and understanding the processes associated with glass alteration under gamma irradiation.« less

Laboratory Testing of Waste Isolation Pilot Plant Surrogate Waste Materials

NASA Astrophysics Data System (ADS)

Broome, S.; Bronowski, D.; Pfeifle, T.; Herrick, C. G.

2011-12-01

The Waste Isolation Pilot Plant (WIPP) is a U.S. Department of Energy geological repository for the permanent disposal of defense-related transuranic (TRU) waste. The waste is emplaced in rooms excavated in the bedded Salado salt formation at a depth of 655 m below the ground surface. After emplacement of the waste, the repository will be sealed and decommissioned. WIPP Performance Assessment modeling of the underground material response requires a full and accurate understanding of coupled mechanical, hydrological, and geochemical processes and how they evolve with time. This study was part of a broader test program focused on room closure, specifically the compaction behavior of waste and the constitutive relations to model this behavior. The goal of this study was to develop an improved waste constitutive model. The model parameters are developed based on a well designed set of test data. The constitutive model will then be used to realistically model evolution of the underground and to better understand the impacts on repository performance. The present study results are focused on laboratory testing of surrogate waste materials. The surrogate wastes correspond to a conservative estimate of the degraded containers and TRU waste materials after the 10,000 year regulatory period. Testing consists of hydrostatic, uniaxial, and triaxial tests performed on surrogate waste recipes that were previously developed by Hansen et al. (1997). These recipes can be divided into materials that simulate 50% and 100% degraded waste by weight. The percent degradation indicates the anticipated amount of iron corrosion, as well as the decomposition of cellulosics, plastics, and rubbers. Axial, lateral, and volumetric strain and axial and lateral stress measurements were made. Two unique testing techniques were developed during the course of the experimental program. The first involves the use of dilatometry to measure sample volumetric strain under a hydrostatic condition. Bulk moduli of the samples measured using this technique were consistent with those measured using more conventional methods. The second technique involved performing triaxial tests under lateral strain control. By limiting the lateral strain to zero by controlling the applied confining pressure while loading the specimen axially in compression, one can maintain a right-circular cylindrical geometry even under large deformations. This technique is preferred over standard triaxial testing methods which result in inhomogeneous deformation or "barreling". Manifestations of the inhomogeneous deformation included non-uniform stress states, as well as unrealistic Poisson's ratios (> 0.5) or those that vary significantly along the length of the specimen. Zero lateral strain controlled tests yield a more uniform stress state, and admissible and uniform values of Poisson's ratio. Hansen, F.D., Knowles, M.K., et al. 1997. Description and Evaluation of a Mechanistically Based Conceptual Model for Spall. SAND97-1369. Sandia National Laboratories, Albuquerque. Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000.

Mitigation of Hydrogen Gas Generation from the Reaction of Uranium Metal with Water in K Basin Sludge and Sludge Waste Forms

DOE Office of Scientific and Technical Information (OSTI.GOV)

Sinkov, Sergey I.; Delegard, Calvin H.; Schmidt, Andrew J.

2011-06-08

Prior laboratory testing identified sodium nitrate and nitrite to be the most promising agents to minimize hydrogen generation from uranium metal aqueous corrosion in Hanford Site K Basin sludge. Of the two, nitrate was determined to be better because of higher chemical capacity, lower toxicity, more reliable efficacy, and fewer side reactions than nitrite. The present lab tests were run to determine if nitrate’s beneficial effects to lower H2 generation in simulated and genuine sludge continued for simulated sludge mixed with agents to immobilize water to help meet the Waste Isolation Pilot Plant (WIPP) waste acceptance drainable liquid criterion. Testsmore » were run at ~60°C, 80°C, and 95°C using near spherical high-purity uranium metal beads and simulated sludge to emulate uranium-rich KW containerized sludge currently residing in engineered containers KW-210 and KW-220. Immobilization agents tested were Portland cement (PC), a commercial blend of PC with sepiolite clay (Aquaset II H), granulated sepiolite clay (Aquaset II G), and sepiolite clay powder (Aquaset II). In all cases except tests with Aquaset II G, the simulated sludge was mixed intimately with the immobilization agent before testing commenced. For the granulated Aquaset II G clay was added to the top of the settled sludge/solution mixture according to manufacturer application directions. The gas volumes and compositions, uranium metal corrosion mass losses, and nitrite, ammonia, and hydroxide concentrations in the interstitial solutions were measured. Uranium metal corrosion rates were compared with rates forecast from the known uranium metal anoxic water corrosion rate law. The ratios of the forecast to the observed rates were calculated to find the corrosion rate attenuation factors. Hydrogen quantities also were measured and compared with quantities expected based on non-attenuated H2 generation at the full forecast anoxic corrosion rate to arrive at H2 attenuation factors. The uranium metal corrosion rates in water alone and in simulated sludge were near or slightly below the metal-in-water rate while nitrate-free sludge/Aquaset II decreased rates by about a factor of 3. Addition of 1 M nitrate to simulated sludge decreased the corrosion rate by a factor of ~5 while 1 M nitrate in sludge/Aquaset II mixtures decreased the corrosion rate by ~2.5 compared with the nitrate-free analogues. Mixtures of simulated sludge with Aquaset II treated with 1 M nitrate had uranium corrosion rates about a factor of 8 to 10 lower than the water-only rate law. Nitrate was found to provide substantial hydrogen mitigation for immobilized simulant sludge waste forms containing Aquaset II or Aquaset II G clay. Hydrogen attenuation factors of 1000 or greater were determined at 60°C for sludge-clay mixtures at 1 M nitrate. Hydrogen mitigation for tests with PC and Aquaset II H (which contains PC) were inconclusive because of suspected failure to overcome induction times and fully enter into anoxic corrosion. Lessening of hydrogen attenuation at ~80°C and ~95°C for simulated sludge and Aquaset II was observed with attenuation factors around 100 to 200 at 1 M nitrate. Valuable additional information has been obtained on the ability of nitrate to attenuate hydrogen gas generation from solution, simulant K Basin sludge, and simulant sludge with immobilization agents. Details on characteristics of the associated reactions were also obtained. The present testing confirms prior work which indicates that nitrate is an effective agent to attenuate hydrogen from uranium metal corrosion in water and simulated K Basin sludge to show that it is also effective in potential candidate solidified K Basin waste forms for WIPP disposal. The hydrogen mitigation afforded by nitrate appears to be sufficient to meet the hydrogen generation limits for shipping various sludge waste streams based on uranium metal concentrations and assumed waste form loadings.« less

Evaluation of the long-term performance of six alternative disposal methods for LLRW

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kossik, R.; Sharp, G.; Chau, T.

1995-12-31

The State of New York has carried out a comparison of six alternative disposal methods for low-level radioactive waste (LLRW). An important part of these evaluations involved quantitatively analyzing the long-term (10,000 yr) performance of the methods with respect to dose to humans, radionuclide concentrations in the environment, and cumulative release from the facility. Four near-surface methods (covered above-grade vault, uncovered above-grade vault, below-grade vault, augered holes) and two mine methods (vertical shaft mine and drift mine) were evaluated. Each method was analyzed for several generic site conditions applicable for the state. The evaluations were carried out using RIP (Repositorymore » Integration Program), an integrated, total system performance assessment computer code which has been applied to radioactive waste disposal facilities both in the U.S. (Yucca Mountain, WIPP) and worldwide. The evaluations indicate that mines in intact low-permeability rock and near-surface facilities with engineered covers generally have a high potential to perform well (within regulatory limits). Uncovered above-grade vaults and mines in highly fractured crystalline rock, however, have a high potential to perform poorly, exceeding regulatory limits.« less

Effects of Heat Generation on Nuclear Waste Disposal in Salt

NASA Astrophysics Data System (ADS)

Clayton, D. J.

2008-12-01

Disposal of nuclear waste in salt is an established technology, as evidenced by the successful operations of the Waste Isolation Pilot Plant (WIPP) since 1999. The WIPP is located in bedded salt in southeastern New Mexico and is a deep underground facility for transuranic (TRU) nuclear waste disposal. There are many advantages for placing radioactive wastes in a geologic bedded-salt environment. One desirable mechanical characteristic of salt is that it flows plastically with time ("creeps"). The rate of salt creep is a strong function of temperature and stress differences. Higher temperatures and deviatoric stresses increase the creep rate. As the salt creeps, induced fractures may be closed and eventually healed, which then effectively seals the waste in place. With a backfill of crushed salt emplaced around the waste, the salt creep can cause the crushed salt to reconsolidate and heal to a state similar to intact salt, serving as an efficient seal. Experiments in the WIPP were conducted to investigate the effects of heat generation on the important phenomena and processes in and around the repository (Munson et al. 1987; 1990; 1992a; 1992b). Brine migration towards the heaters was induced from the thermal gradient, while salt creep rates showed an exponential dependence on temperature. The project "Backfill and Material Behavior in Underground Salt Repositories, Phase II" (BAMBUS II) studied the crushed salt backfill and material behavior with heat generation at the Asse mine located near Remlingen, Germany (Bechthold et al. 2004). Increased salt creep rates and significant reconsolidation of the crushed salt were observed at the termination of the experiment. Using the data provided from both projects, exploratory modeling of the thermal-mechanical response of salt has been conducted with varying thermal loading and waste spacing. Increased thermal loading and decreased waste spacing drive the system to higher temperatures, while both factors are desired to reduce costs, as well as decrease the overall footprint of the repository. Higher temperatures increase the rate of salt creep which then effectively seals the waste quicker. Data of the thermal-mechanical response of salt at these higher temperatures is needed to further validate the exploratory modeling and provide meaningful constraints on the repository design. Sandia is a multi program laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy's National Nuclear Security Administration under Contract DE-AC04- 94AL85000.

RH-TRU Waste Shipments from Battelle Columbus Laboratories to the Hanford Nuclear Facility for Interim Storage

DOE Office of Scientific and Technical Information (OSTI.GOV)

Eide, J.; Baillieul, T. A.; Biedscheid, J.

2003-02-26

Battelle Columbus Laboratories (BCL), located in Columbus, Ohio, must complete decontamination and decommissioning (D&D) activities for nuclear research buildings and grounds by 2006, as directed by Congress. Most of the resulting waste (approximately 27 cubic meters [m3]) is remote-handled (RH) transuranic (TRU) waste destined for disposal at the Waste Isolation Pilot Plant (WIPP). The BCL, under a contract to the U.S. Department of Energy (DOE) Ohio Field Office, has initiated a plan to ship the TRU waste to the DOE Hanford Nuclear Facility (Hanford) for interim storage pending the authorization of WIPP for the permanent disposal of RH-TRU waste. Themore » first of the BCL RH-TRU waste shipments was successfully completed on December 18, 2002. This BCL shipment of one fully loaded 10-160B Cask was the first shipment of RH-TRU waste in several years. Its successful completion required a complex effort entailing coordination between different contractors and federal agencies to establish necessary supporting agreements. This paper discusses the agreements and funding mechanisms used in support of the BCL shipments of TRU waste to Hanford for interim storage. In addition, this paper presents a summary of the efforts completed to demonstrate the effectiveness of the 10-160B Cask system. Lessons learned during this process are discussed and may be applicable to other TRU waste site shipment plans.« less

Field-scale Thermal Testing in a Generic Salt Disposal Environment Underground Research Laboratory (URL): Delineation of Principal Purpose Objectives and Hypotheses

DOE Office of Scientific and Technical Information (OSTI.GOV)

Sassani, David C.; Hardin, Ernest L.; Kuhlman, Kristopher L

The amount of brine present in domal salt formation is far less than in bedded salts (e.g., 0.01 to 0.1% compared with 1 to 3%). In salt domes, shear deformation associated with diapirism has caused existing brine to coalesce, leading to flow and expulsion. Brine migration behavior was investigated in bedded salt at WIPP (Nowak and McTigue 1987, SAND87-0880), and in domal salt at Asse (Coyle et al. 1987, BMI/ONWI-624). Test methods were not standardized, and the tests involved large diameter boreholes (17 to 36 in. diameter) and large apparatus. The tested intervals were proximal to mined openings (within approximatelymore » 1 diameter) where in situ stresses are redistributed due to excavation. The tests showed that (1) brine inflow rates can range over at least 2 orders of magnitude for domal vs. bedded salt, (2) that brine inflow is strongly associated with clay and interbedded permeable layers in bedded salt, and (3) that measurement systems can readily collect very small quantities of moisture over time frames of 2 years or longer. Brine inflow rates declined slightly with time in both test series, but neither series approached a state of apparent depletion. This range of flow magnitude could be significant to repository design and performance assessment, especially if inflow rates can be predicted using stratigraphic and geomechanical inputs, and can be shown to approach zero in a predictable manner.« less

The second iteration of the Systems Prioritization Method: A systems prioritization and decision-aiding tool for the Waste Isolation Pilot Plant: Volume 2, Summary of technical input and model implementation

DOE Office of Scientific and Technical Information (OSTI.GOV)

Prindle, N.H.; Mendenhall, F.T.; Trauth, K.

1996-05-01

The Systems Prioritization Method (SPM) is a decision-aiding tool developed by Sandia National Laboratories (SNL). SPM provides an analytical basis for supporting programmatic decisions for the Waste Isolation Pilot Plant (WIPP) to meet selected portions of the applicable US EPA long-term performance regulations. The first iteration of SPM (SPM-1), the prototype for SPM< was completed in 1994. It served as a benchmark and a test bed for developing the tools needed for the second iteration of SPM (SPM-2). SPM-2, completed in 1995, is intended for programmatic decision making. This is Volume II of the three-volume final report of the secondmore » iteration of the SPM. It describes the technical input and model implementation for SPM-2, and presents the SPM-2 technical baseline and the activities, activity outcomes, outcome probabilities, and the input parameters for SPM-2 analysis.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Guo, Xiaofeng; Xu, Hongwu

Polyhalite is an important coexisting mineral with halite in salt repositories for nuclear waste disposal, such as Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The thermal stability of this mineral is a key knowledge in evaluating the integrity of a salt repository in the long term, as water may release due to thermal decomposition of polyhalite. Previous studies on structural evolution of polyhalite at elevated temperatures laid the basis for detailed calorimetric measurements. Using high-temperature oxide-melt drop-solution calorimetry at 975 K with sodium molybdate as the solvent, we have determined the standard enthalpies of formation from constituent sulfatesmore » (ΔH° f,sul), oxides (ΔH° f,ox) and elements (ΔH° f,ele) of a polyhalite sample with the composition of K 2Ca 2Mg(SO 4) 4·1.95H 2O from the Salado formation at the WIPP site. The obtained results are: ΔH° f,sul = -152.5 ± 5.3 kJ/mol, ΔH° f,ox = -1926.1 ± 10.5 kJ/mol, and ΔH° f,ele = -6301.2 ± 9.9 kJ/mol. Furthermore, based on the estimated formation entropies of polyhalite, its standard Gibbs free energy of formation has been derived to be in the range of -5715.3 ± 9.9 kJ/mol to -5739.3 ± 9.9 kJ/mol. In conclusion, these determined thermodynamic properties provide fundamental parameters for modeling the stability behavior of polyhalite in salt repositories.« less

Expert System for Building TRU Waste Payloads - 13554

DOE Office of Scientific and Technical Information (OSTI.GOV)

Bruemmer, Heather; Slater, Bryant

2013-07-01

The process for grouping TRU waste drums into payloads for shipment to the Waste Isolation Pilot Plant (WIPP) for disposal is a very complex process. Transportation and regulatory requirements must be met, along with striving for the goals of shipment efficiency: maximize the number of waste drums in a shipment and minimize the use of empty drums which take up precious underground storage space. The restrictions on payloads range from weight restrictions, to limitations on flammable gas in the headspace, to minimum TRU alpha activity concentration requirements. The Overpack and Payload Assistant Tool (OPAT) has been developed as a mixed-initiativemore » intelligent system within the WIPP Waste Data System (WDS) to guide the construction of multiple acceptable payloads. OPAT saves the user time while at the same time maximizes the efficiency of shipments for the given drum population. The tool provides the user with the flexibility to tune critical factors that guide OPAT's operation based on real-time feedback concerning the results of the execution. This feedback complements the user's external knowledge of the drum population (such as location of drums, known challenges, internal shipment goals). This work demonstrates how software can be utilized to complement the unique domain knowledge of the users. The mixed-initiative approach combines the insight and intuition of the human expert with the proficiency of automated computational algorithms. The result is the ability to thoroughly and efficiently explore the search space of possible solutions and derive the best waste management decision. (authors)« less

Sorbent Scoping Studies

DOE Office of Scientific and Technical Information (OSTI.GOV)

Chancellor, Christopher John

2016-11-14

The Los Alamos National Laboratory–Carlsbad Operations (LANL-CO) office was tasked by the DOE CBFO, Office of the Manager to perform a review of the acceptable knowledge (AK) to identify the oxidizers and sorbents in transuranic (TRU) waste streams, to conduct scoping studies on the oxidizers and sorbents identified in AK review to inform the Quality Level 1 (QL1) testing, and to conduct a series of QL1 tests to provide the scientific data to support a basis of knowledge document for determining the criteria for (1) accepting waste at the Waste Isolation Pilot Plant (WIPP) without treatment, (2) determining waste thatmore » will require treatment, and (3) if treatment is required, how the treatment must be performed. The purpose of this report is to present the results of the AK review of sorbents present in active waste streams, provide a technical analysis of the sorbent list, report the results of the scoping studies for the fastest-burning organic sorbent, and provide the list of organic and inorganic sorbents to be used in the development of a Test Plan for Preparation and Testing of Sorbents Mixed with Oxidizer found in Transuranic Waste (DWT-TP-001). The companion report, DWT-RPT-001, Oxidizer Scoping Studies, has similar information for oxidizers identified during the AK review of TRU waste streams. The results of the oxidizer and sorbent scoping studies will be used to inform the QL1 test plan. The QL1 test results will support the development of a basis of knowledge document that will evaluate oxidizing chemicals and sorbents in TRU waste and provide guidance for treatment.« less

VITRIFICATION SYSTEM FOR THE TREATMENT OF PLUTONIUM-BEARING WASTE AT LOS ALAMOS NATIONAL LABORATORY

DOE Office of Scientific and Technical Information (OSTI.GOV)

R. NAKAOKA; G. VEAZEY; ET AL

2001-05-01

A glove box vitrification system is being fabricated to process aqueous evaporator bottom waste generated at the Plutonium Facility (TA-55) at Los Alamos National Laboratory (LANL). The system will be the first within the U.S. Department of Energy Complex to routinely convert Pu{sup 239}-bearing transuranic (TRU) waste to a glass matrix for eventual disposal at the Waste Isolation Pilot Plant (WIPP). Currently at LANL, this waste is solidified in Portland cement. Radionuclide loading in the cementation process is restricted by potential radiolytic degradation (expressed as a wattage limit), which has been imposed to prevent the accumulation of flammable concentrations ofmore » H{sub 2} within waste packages. Waste matrixes with a higher water content (e.g., cement) are assigned a lower permissible wattage limit to compensate for their potential higher generation of H{sub 2}. This significantly increases the number of waste packages that must be prepared and shipped, thus driving up the costs of waste handling and disposal. The glove box vitrification system that is under construction will address this limitation. Because the resultant glass matrix produced by the vitrification process is non-hydrogenous, no H{sub 2} can be radiolytically evolved, and drums could be loaded to the maximum allowable limit of 40 watts. In effect, the glass waste form shifts the limiting constraint for loading disposal drums from wattage to the criticality limit of 200 fissile gram equivalents, thus significantly reducing the number of drums generated from this waste stream. It is anticipated that the number of drums generated from treatment of evaporator bottoms will be reduced by a factor of 4 annually when the vitrification system is operational. The system is currently undergoing non-radioactive operability testing, and will be fully operational in the year 2003.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Dewers, Thomas; Heath, Jason E.; Leigh, Christi D.

The nature of geologic disposal of nuclear waste in salt formations requires validated and verified two-phase flow models of transport of brine and gas through intact, damaged, and consolidating crushed salt. Such models exist in other realms of subsurface engineering for other lithologic classes (oil and gas, carbon sequestration etc. for clastics and carbonates) but have never been experimentally validated and parameterized for salt repository scenarios or performance assessment. Models for waste release scenarios in salt back-fill require phenomenological expressions for capillary pressure and relative permeability that are expected to change with degree of consolidation, and require experimental measurement tomore » parameterize and validate. This report describes a preliminary assessment of the influence of consolidation (i.e. volume strain or porosity) on capillary entry pressure in two phase systems using mercury injection capillary pressure (MICP). This is to both determine the potential usefulness of the mercury intrusion porosimetry method, but also to enable a better experimental design for these tests. Salt consolidation experiments are performed using novel titanium oedometers, or uniaxial compression cells often used in soil mechanics, using sieved run-of-mine salt from the Waste Isolation Pilot Plant (WIPP) as starting material. Twelve tests are performed with various starting amounts of brine pore saturation, with axial stresses up to 6.2 MPa (~900 psi) and temperatures to 90°C. This corresponds to UFD Work Package 15SN08180211 milestone “FY:15 Transport Properties of Run-of-Mine Salt Backfill – Unconsolidated to Consolidated”. Samples exposed to uniaxial compression undergo time-dependent consolidation, or creep, to various degrees. Creep volume strain-time relations obey simple log-time behavior through the range of porosities (~50 to 2% as measured); creep strain rate increases with temperature and applied stress as expected. Mercury porosimetry is used to determine characteristic capillary pressure curves from a series of consolidation tests and show characteristic saturation-capillary pressure curves that follow the common van Genuchten (1978, 1980) formulation at low stresses. Higher capillary pressure data are suspect due to the large potential for sample damage, including fluid inclusion decrepitation and pore collapse. Data are supportive of use of the Leverett “J” function (Leverett, 1941) to use for scaling characteristic curves at different degrees of consolidation, but better permeability determinations are needed to support this hypothesis. Recommendations for further and refined testing are made with the goal of developing a self- consistent set of constitutive laws for granular salt consolidation and multiphase (brine-air) flow.« less

Enthalpies of formation of polyhalite: A mineral relevant to salt repository

DOE PAGES

Guo, Xiaofeng; Xu, Hongwu

2017-06-02

Polyhalite is an important coexisting mineral with halite in salt repositories for nuclear waste disposal, such as Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The thermal stability of this mineral is a key knowledge in evaluating the integrity of a salt repository in the long term, as water may release due to thermal decomposition of polyhalite. Previous studies on structural evolution of polyhalite at elevated temperatures laid the basis for detailed calorimetric measurements. Using high-temperature oxide-melt drop-solution calorimetry at 975 K with sodium molybdate as the solvent, we have determined the standard enthalpies of formation from constituent sulfatesmore » (ΔH° f,sul), oxides (ΔH° f,ox) and elements (ΔH° f,ele) of a polyhalite sample with the composition of K 2Ca 2Mg(SO 4) 4·1.95H 2O from the Salado formation at the WIPP site. The obtained results are: ΔH° f,sul = -152.5 ± 5.3 kJ/mol, ΔH° f,ox = -1926.1 ± 10.5 kJ/mol, and ΔH° f,ele = -6301.2 ± 9.9 kJ/mol. Furthermore, based on the estimated formation entropies of polyhalite, its standard Gibbs free energy of formation has been derived to be in the range of -5715.3 ± 9.9 kJ/mol to -5739.3 ± 9.9 kJ/mol. In conclusion, these determined thermodynamic properties provide fundamental parameters for modeling the stability behavior of polyhalite in salt repositories.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Gruetzmacher, Kathleen M.; Bustos, Roland M.; Ferran, Scott G.

Los Alamos National Laboratory (LANL) uses the Nevada National Security Site (NNSS) as an off-site disposal facility for low-level waste (LLW), including sludge waste. NNSS has issued a position paper that indicates that systems that are not certified by the Carlsbad Field Office (CBFO) for Waste Isolation Pilot Plant (WIPP) disposal of Transuranic (TRU) waste must demonstrate equivalent practices to the CBFO certified systems in order to assign activity concentration values to assayed items without adding in the Total Measurement Uncertainty (TMU) when certifying waste for NNSS disposal. Efforts have been made to meet NNSS requirements to accept sludge wastemore » for disposal at their facility. The LANL LLW Characterization Team uses portable high purity germanium (HPGe) detector systems for the nondestructive assay (NDA) of both debris and sludge LLW. A number of performance studies have been conducted historically by LANL to support the efficacy and quality of assay results generated by the LANL HPGe systems, and, while these detector systems are supported by these performance studies and used with LANL approved procedures and processes, they are not certified by CBFO for TRU waste disposal. Beginning in 2009, the LANL LLW Characterization Team undertook additional NDA measurements of both debris and sludge simulated waste containers to supplement existing studies and procedures to demonstrate full compliance with the NNSS position paper. Where possible, Performance Demonstration Project (PDP) drums were used for the waste matrix and PDP sources were used for the radioactive sources. Sludge drums are an example of a matrix with a uniform distribution of contaminants. When attempting to perform a gamma assay of a sludge drum, it is very important to adequately simulate this uniform distribution of radionuclides in order to accurately model the assay results. This was accomplished by using a spiral radial source tube placement in a sludge drum rather than the standard three source tubes seen in debris PDP drums. Available line sources (Eu-152) were placed in the spiral tubes to further accomplish the desired uniform distribution of radionuclides. The standard PDP drum (PDP matrix drum 005) and PDP sources were used to determine the lower limits of detection (LLD) and TMU. Analysis results for the sludge drum matrix case for two HPGe detectors were tabulated and evaluated. NNSS has accepted the methodology and results of the measurements towards demonstrating equivalence to CBFO certified systems. In conclusion, the WES-WGS and CMR-OPS gamma spectroscopy teams at LANL have defined and performed measurements that serve to establish and demonstrate equivalency with the processes used by CBFO certified NDA systems. The supplemental measurements address four key areas in Appendix A of DOE/WIPP-02-3122: Annual Calibration Confirmation and Performance Check measurements; LLD determination; and TMU definition. For these measurements the containers, matrices and activity loadings are selected to represent items being assayed in real LLW cases. The LLD and the TMU bounding measurements are to be performed one time and will not be required to be repeated in future campaigns. The annual calibration and performance check measurements were performed initially and planned to repeat in annual campaigns in order to maintain NNSS certification. PDP sources and a PDP sludge drum as well as Eu-152 line sources and a spiral sludge drum were used for the measurements. In all cases, the results for accuracy and precision (%R and %RSD, respectively) were within allowable ranges as defined by the WIPP PDP program. LLD (or MDC) results were established for all the ten WIPP reportable radionuclides and U-235, and the MDC for Pu-239 was established in all cases to be well under 100 nCi/g. Useful results for reducing estimated uncertainties were established and an interesting unexpected case of high bias was observed and will be applied toward this end. (authors)« less

Hydrothermal Testing of K Basin Sludge and N Reactor Fuel at Sludge Treatment Project Operating Conditions

DOE Office of Scientific and Technical Information (OSTI.GOV)

Delegard, Calvin H.; Schmidt, Andrew J.; Thornton, Brenda M.

The Sludge Treatment Project (STP), managed for the U. S. DOE by Fluor Hanford (FH), was created to design and operate a process to eliminate uranium metal from K Basin sludge prior to packaging for Waste Isolation Pilot Plant (WIPP). The STP process uses high temperature liquid water to accelerate the reaction, produce uranium dioxide from the uranium metal, and safely discharge the hydrogen. Under nominal process conditions, the sludge will be heated in pressurized water at 185°C for as long as 72 hours to assure the complete reaction (corrosion) of up to 0.25-inch diameter uranium metal pieces. Under contractmore » to FH, the Pacific Northwest National Laboratory (PNNL) conducted bench-scale testing of the STP hydrothermal process in November and December 2006. Five tests (~50 ml each) were conducted in sealed, un-agitated reaction vessels under the hydrothermal conditions (e.g., 7 to 72 h at 185°C) of the STP corrosion process using radioactive sludge samples collected from the K East Basin and particles/coupons of N Reactor fuel also taken from the K Basins. The tests were designed to evaluate and understand the chemical changes that may be occurring and the effects that any changes would have on sludge rheological properties. The tests were not designed to evaluate engineering aspects of the process. The hydrothermal treatment affected the chemical and physical properties of the sludge. In each test, significant uranium compound phase changes were identified, resulting from dehydration and chemical reduction reactions. Physical properties of the sludge were significantly altered from their initial, as-settled sludge values, including, shear strength, settled density, weight percent water, and gas retention.« less

An x-ray absorption spectroscopy study of Cd binding onto a halophilic archaeon

NASA Astrophysics Data System (ADS)

Showalter, Allison R.; Szymanowski, Jennifer E. S.; Fein, Jeremy B.; Bunker, Bruce A.

2016-05-01

X-ray absorption spectroscopy (XAS) and cadmium (Cd) isotherm experiments determine how Cd adsorbs to the surface of halophilic archaeon Halobacterium noricense. This archaeon, isolated from the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico could be involved with the transport of toxic metals stored in the transuranic waste in the salt mine. The isotherm experiments show that adsorption is relatively constant across the tolerable pH range for H. noricense. The XAS results indicate that Cd adsorption occurs predominately via a sulfur site, most likely sulfhydryl, with the same site dominating all measured pH values.

Effect of oxidation state and ionic strength on sorption of actinides (Th, U, Np, Am) to geologic media [Abstract and References Only

DOE Office of Scientific and Technical Information (OSTI.GOV)

Dittrich, Timothy M.; Richmann, Michael K.; Reed, Donald T.

2015-10-30

The degree of conservatism in the estimated sorption partition coefficients (K ds) used in a performance assessment model is being evaluated based on a complementary batch and column method. The main focus of this work is to investigate the role of ionic strength, solution chemistry, and oxidation state (III-VI) in actinide sorption to dolomite rock. Based on redox conditions and solution chemistry expected at the WIPP, possible actinide species include Pu(III), Pu(IV), U(IV), U(VI), Np(IV), Np(V), Am(III), and Th(IV).

Summary Report of Comprehensive Laboratory Testing to Establish the Effectiveness of Proposed Treatment Methods for Unremediated and Remediated Nitrate Salt Waste Streams

DOE Office of Scientific and Technical Information (OSTI.GOV)

Anast, Kurt Roy; Funk, David John; Hargis, Kenneth Marshall

The inadvertent creation of transuranic waste carrying hazardous waste codes D001 and D002 requires the treatment of the material to eliminate the hazardous characteristics and allow its eventual shipment and disposal at the Waste Isolation Pilot Plant (WIPP). This report documents the effectiveness of two treatment methods proposed to stabilize both the unremediated and remediated nitrate salt waste streams (UNS and RNS, respectively) at Los Alamos National Laboratory (LANL). The two technologies include the addition of zeolite (with and without the addition of water as a processing aid) and cementation. Surrogates were developed to evaluate both the solid and liquidmore » fractions expected from parent waste containers, and both the solid and liquid fractions were tested. Both technologies are shown to be effective at eliminating the characteristic of ignitability (D001), and the addition of zeolite was determined to be effective at eliminating corrosivity (D002), with the preferred option1 of adding zeolite currently planned for implementation at LANL’s Waste Characterization, Reduction, and Repackaging Facility (WCRRF). The course of this work verified the need to evaluate and demonstrate the effectiveness of the proposed remedy for debris material, if required. The evaluation determined that WypAlls, cheesecloth, and Celotex absorbed with saturated nitrate salt solutions exhibit the ignitability characteristic (all other expected debris is not classified as ignitable). Finally, liquid surrogates containing saturated nitrate salts did not exhibit the characteristic of ignitability in their pure form (those neutralized with Kolorsafe and mixed with sWheat did exhibit D001). Sensitivity testing and an analysis were conducted to evaluate the waste form for reactivity. Tests included subjecting surrogate material to mechanical impact, friction, electrostatic discharge and thermal insults. The testing confirmed that the waste does not exhibit the characteristic of reactivity (D003). Follow-on testing was conducted to demonstrate the effectiveness of zeolite stabilization for ignitable WypAll and cheesecloth debris and additional nitrate salt solutions (those exhibiting the oxidizer characteristic) to demonstrate the effectiveness of the remedy. Follow-on testing also included testing of surrogate materials containing Waste Lock 770, which is present in four of the RNS containers, and potential items of debris such as plywood and Celotex material. Testing to evaluate the effectiveness of the remedy was performed using the specific remediation processes that are planned for use at the WCRRF. Finally, testing was also performed to evaluate the holding capacity of zeolite using a highly acidic surrogate solution and to characterize the composition of gases generated during mixing of zeolite with surrogate solutions. All these tests demonstrated the effectiveness of adding zeolite as the planned remedy.« less

Cookoff Modeling of a WIPP waste drum (68660)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hobbs, Michael L.

2014-11-24

A waste drum located 2150 feet underground may have been the root cause of a radiation leak on February 14, 2014. Information provided to the WIPP Technical Assessment Team (TAT) was used to describe the approximate content of the drum, which included an organic cat litter (Swheat Scoop®, or Swheat) composed of 100% wheat products. The drum also contained various nitrate salts, oxalic acid, and a nitric acid solution that was neutralized with triethanolamine (TEA). CTH-TIGER was used with the approximate drum contents to specify the products for an exothermic reaction for the drum. If an inorganic adsorbent such asmore » zeolite had been used in lieu of the kitty litter, the overall reaction would have been endothermic. Dilution with a zeolite adsorbent might be a useful method to remediate drums containing organic kitty litter. SIERRA THERMAL was used to calculate the pressurization and ignition of the drum. A baseline simulation of drum 68660 was performed by assuming a background heat source of 0.5-10 W of unknown origin. The 0.5 W source could be representative of heat generated by radioactive decay. The drum ignited after about 70 days. Gas generation at ignition was predicted to be 300-500 psig with a sealed drum (no vent). At ignition, the wall temperature increases modestly by about 1°C, demonstrating that heating would not be apparent prior to ignition. The ignition location was predicted to be about 0.43 meters above the bottom center portion of the drum. At ignition only 3-5 kg (out of 71.6 kg total) has been converted into gas, indicating that most of the material remained available for post-ignition reaction.« less

Geochemical evolution of groundwater in the Culebra dolomite near the Waste Isolation Pilot Plant, southeastern New Mexico, USA

USGS Publications Warehouse

Siegel, M.D.; Anderholm, S.

1994-01-01

The Culebra Dolomite Member of the Rustler Formation, a thin (10 m) fractured dolomite aquifer, lies approximately 450 m above the repository horizon of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico, USA. Salinities of water in the Culebra range roughly from 10,000 to 200,000 mg/L within the WIPP site. A proposed model for the post-Pleistocene hydrochemical evolution of the Culebra tentatively identifies the major sources and sinks for many of the groundwater solutes. Reaction-path simulations with the PHRQPITZ code suggest that the Culebra dolomite is a partial chemical equilibrium system whose composition is controlled by an irreversible process (dissolution of evaporites) and equilibrium with gypsum and calcite. Net geochemical reactions along postulated modern flow paths, calculated with the NETPATH code, include dissolution of halite, carbonate and evaporite salts, and ion exchange. R-mode principal component analysis revealed correlations among the concentrations of Si, Mg, pH, Li, and B that are consistent with several clay-water reactions. The results of the geochemical calculations and mineralogical data are consistent with the following hydrochemical model: 1. (1) solutes are added to the Culebra by dissolution of evaporite minerals 2. (2) the solubilities of gypsum and calcite increase as the salinity increases; these minerals dissolve as chemical equilibrium is maintained between them and the groundwater 3. (3) equilibrium is not maintained between the waters and dolomite; sufficient Mg is added to the waters by dissolution of accessory carnallite or polyhalite such that the degree of dolomite supersaturation increases with ionic strength 4. (4) clays within the fractures and rock matrix exert some control on the distribution of Li, B, Mg, and Si via sorption, ion exchange, and dissolution. ?? 1994.

Small-Scale Experiments.10-gallon drum experiment summary

DOE Office of Scientific and Technical Information (OSTI.GOV)

Rosenberg, David M.

2015-02-05

A series of sub-scale (10-gallon) drum experiments were conducted to characterize the reactivity, heat generation, and gas generation of mixtures of chemicals believed to be present in the drum (68660) known to have breached in association with the radiation release event at the Waste Isolation Pilot Plant (WIPP) on February 14, 2014, at a scale expected to be large enough to replicate the environment in that drum but small enough to be practical, safe, and cost effective. These tests were not intended to replicate all the properties of drum 68660 or the event that led to its breach, or tomore » validate a particular hypothesis of the release event. They were intended to observe, in a controlled environment and with suitable diagnostics, the behavior of simple mixtures of chemicals in order to determine if they could support reactivity that could result in ignition or if some other ingredient or event would be necessary. There is a significant amount of uncertainty into the exact composition of the barrel; a limited sub-set of known components was identified, reviewed with Technical Assessment Team (TAT) members, and used in these tests. This set of experiments was intended to provide a framework to postulate realistic, data-supported hypotheses for processes that occur in a “68660-like” configuration, not definitively prove what actually occurred in 68660.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Sailer, S.J.

This Quality Assurance Project Plan (QAPJP) specifies the quality of data necessary and the characterization techniques employed at the Idaho National Engineering Laboratory (INEL) to meet the objectives of the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Transuranic Waste Characterization Quality Assurance Program Plan (QAPP) requirements. This QAPJP is written to conform with the requirements and guidelines specified in the QAPP and the associated documents referenced in the QAPP. This QAPJP is one of a set of five interrelated QAPjPs that describe the INEL Transuranic Waste Characterization Program (TWCP). Each of the five facilities participating in the TWCPmore » has a QAPJP that describes the activities applicable to that particular facility. This QAPJP describes the roles and responsibilities of the Idaho Chemical Processing Plant (ICPP) Analytical Chemistry Laboratory (ACL) in the TWCP. Data quality objectives and quality assurance objectives are explained. Sample analysis procedures and associated quality assurance measures are also addressed; these include: sample chain of custody; data validation; usability and reporting; documentation and records; audits and 0385 assessments; laboratory QC samples; and instrument testing, inspection, maintenance and calibration. Finally, administrative quality control measures, such as document control, control of nonconformances, variances and QA status reporting are described.« less

Geotechnical Field Data and Analysis Report, July 1991--June 1992. Volume 1

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1993-09-01

The Geotechnical Field Data and Analysis Report documents the geotechnical data from the underground excavations at the Waste Isolation Pilot Plant (WIPP) located near Carlsbad, New Mexico. The data are used to characterize conditions, confirm design assumptions, and understand and predict the performance of the underground excavations during operations. The data are obtained as part of a routine monitoring program and do not include data from tests performed by Sandia National Laboratories (SNL), the Scientific Advisor to the project, in support of performance assessment studies. The purpose of the geomechanical monitoring program is to provide in situ data to supportmore » continuing assessments of the design for the underground facilities. Specifically, the program provides: Early detection of conditions that could compromise operational safety; evaluation of room closure to ensure retrievability of waste; guidance for design modifications and remedial actions; and data for interpreting the actual behavior of underground openings, in comparison with established design criteria. This Geotechnical Field Data and Analysis Report covers the period July 1, 1991 to June 30, 1992. Volume 1 provides an interpretation of the field data while Volume 2 describes and presents the data itself.« less

Pipe Overpack Container Fire Testing: Phase I II & III.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Figueroa, Victor G.; Ammerman, Douglas J.; Lopez, Carlos

The Pipe Overpack Container (POC) was developed at Rocky Flats to transport plutonium residues with higher levels of plutonium than standard transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) for disposal. In 1996 Sandia National Laboratories (SNL) conducted a series of tests to determine the degree of protection POCs provided during storage accident events. One of these tests exposed four of the POCs to a 30-minute engulfing pool fire, resulting in one of the 7A drum overpacks generating sufficient internal pressure to pop off its lid and expose the top of the pipe container (PC) to the firemore » environment. The initial contents of the POCs were inert materials, which would not generate large internal pressure within the PC if heated. POCs are now being used to store combustible TRU waste at Department of Energy (DOE) sites. At the request of DOE’s Office of Environmental Management (EM) and National Nuclear Security Administration (NNSA), starting in 2015 SNL conducted a series of fire tests to examine whether PCs with combustibles would reach a temperature that would result in (1) decomposition of inner contents and (2) subsequent generation of sufficient gas to cause the PC to over-pressurize and release its inner content. Tests conducted during 2015 and 2016 were done in three phases. The goal of the first phase was to see if the PC would reach high enough temperatures to decompose typical combustible materials inside the PC. The goal of the second test phase was to determine under what heating loads (i.e., incident heat fluxes) the 7A drum lid pops off from the POC drum. The goal of the third phase was to see if surrogate aerosol gets released from the PC when the drum lid is off. This report will describe the various tests conducted in phase I, II, and III, present preliminary results from these tests, and discuss implications for the POCs.« less

Pipe Overpack Container Fire Testing: Phase I & II

DOE Office of Scientific and Technical Information (OSTI.GOV)

Figueroa, Victor G.; Ammerman, Douglas J.; Lopez, Carlos

The Pipe Overpack Container (POC) was developed at Rocky Flats to transport plutonium residues with higher levels of plutonium than standard transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) for disposal. In 1996 Sandia National Laboratories (SNL) conducted a series of tests to determine the degree of protection POCs provided during storage accident events. One of these tests exposed four of the POCs to a 30-minute engulfing pool fire, resulting in one of the 7A drum overpacks generating sufficient internal pressure to pop off its lid and expose the top of the pipe container (PC) to the firemore » environment. The initial contents of the POCs were inert materials, which would not generate large internal pressure within the PC if heated. However, POCs are now being used to store combustible TRU waste at Department of Energy (DOE) sites. At the request of DOE’s Office of Environmental Management (EM) and National Nuclear Security Administration (NNSA), starting in 2015 SNL conducted a new series of fire tests to examine whether PCs with combustibles would reach a temperature that would result in (1) decomposition of inner contents and (2) subsequent generation of sufficient gas to cause the PC to over-pressurize and release its inner content. Tests conducted during 2015 and 2016, and described herein, were done in two phases. The goal of the first phase was to see if the PC would reach high enough temperatures to decompose typical combustible materials inside the PC. The goal of the second test phase was to determine under what heating loads (i.e., incident heat fluxes) the 7A drum lid pops off from the POC drum. This report will describe the various tests conducted in phase I and II, present preliminary results from these tests, and discuss implications for the POCs.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Humphrey, Betty; Bland, Jesse John

This paper documents the history of the TRU program at Sandia, previous and current activities associated with TRU material and waste, interfaces with other TRU waste generator sites and the Waste Isolation Pilot Plan (WIPP), and paths forward for TRU material and waste. This document is a snapshot in time of the TRU program and should be updated as necessary, or when significant changes have occurred in the Sandia TRU program or in the TRU regulatory environment. This paper should serve as a roadmap to capture past TRU work so that efforts are not repeated and ground is not lostmore » due to future inactivity and personnel changes.« less

Dangerous Waste Characteristics of Contact-Handled Transuranic Mixed Wastes from Hanford Tanks

DOE Office of Scientific and Technical Information (OSTI.GOV)

Tingey, Joel M.; Bryan, Garry H.; Deschane, Jaquetta R.

2004-10-05

This report summarizes existing analytical data gleaned from samples taken from the Hanford tanks designated as potentially containing transuranic mixed process wastes. Process knowledge of the wastes transferred to these tanks has been reviewed to determine whether the dangerous waste characteristics now assigned to all Hanford underground storage tanks are applicable to these particular wastes. Supplemental technologies are being examined to accelerate the Hanford tank waste cleanup mission and accomplish waste treatment safely and efficiently. To date, 11 Hanford waste tanks have been designated as potentially containing contact-handled (CH) transuranic mixed (TRUM) wastes. The CH-TRUM wastes are found in single-shellmore » tanks B-201 through B-204, T-201 through T-204, T-104, T-110, and T-111. Methods and equipment to solidify and package the CH-TRUM wastes are part of the supplemental technologies being evaluated. The resulting packages and wastes must be acceptable for disposal at the Waste Isolation Pilot Plant (WIPP). The dangerous waste characteristics being considered include ignitability, corrosivity, reactivity, and toxicity arising from the presence of 2,4,5-trichlorophenol at levels above the dangerous waste threshold. The analytical data reviewed include concentrations of sulfur, sulfate, cyanide, 2,4,5-trichlorophenol, total organic carbon, and oxalate; the composition of the tank headspace, pH, and mercury. Differential scanning calorimetry results were used to determine the energetics of the wastes as a function of temperature. This report supercedes and replaces PNNL-14832.« less

Dangerous Waste Characteristics of Contact-Handled Transuranic Mixed Wastes from the Hanford Tanks

DOE Office of Scientific and Technical Information (OSTI.GOV)

Tingey, Joel M.; Bryan, Garry H.; Deschane, Jaquetta R.

2004-08-31

This report summarizes existing analytical data from samples taken from the Hanford tanks designated as potentially containing transuranic mixed process wastes. Process knowledge of the wastes transferred to these tanks has been reviewed to determine whether the dangerous waste characteristics now assigned to all Hanford underground storage tanks are applicable to these particular wastes. Supplemental technologies are being examined to accelerate the Hanford tank waste cleanup mission and accomplish waste treatment safely and efficiently. To date, 11 Hanford waste tanks have been designated as potentially containing contact-handled (CH) transuranic mixed (TRUM) wastes. The CH-TRUM wastes are found in single-shell tanksmore » B-201 through B-204, T-201 through T-204, T-104, T-110, and T-111. Methods and equipment to solidify and package the CH-TRUM wastes are part of the supplemental technologies being evaluated. The resulting packages and wastes must be acceptable for disposal at the Waste Isolation Pilot Plant (WIPP). The dangerous waste characteristics being considered include ignitability, corrosivity, reactivity, and toxicity arising from the presence of 2,4,5-trichlorophenol at levels above the dangerous waste threshold. The analytical data reviewed include concentrations of sulfur, sulfate, cyanide, 2,4,5-trichlorophenol, total organic carbon, and oxalate; the composition of the tank headspace, pH, and mercury. Differential scanning calorimetry results were used to determine the energetics of the wastes as a function of temperature.« less

Reconsolidation of Crushed Salt to 250°C Under Hydrostatic and Shear Stress Conditions Scott Broome, Frank Hansen, and SJ Bauer Sandia National Laboratories, Geomechanics Department

NASA Astrophysics Data System (ADS)

Broome, S. T.

2012-12-01

Design, analysis and performance assessment of potential salt repositories for heat-generating nuclear waste require knowledge of thermal, mechanical, and fluid transport properties of reconsolidating granular salt. Mechanical properties, Bulk (K) and Elastic (E) Moduli and Poisson's ratio (ν) are functions of porosity which decreases as the surrounding salt creeps inward and compresses granular salt within the rooms, drifts or shafts. To inform salt repository evaluations, we have undertaken an experimental program to determine K, E, and ν of reconsolidated granular salt as a function of porosity and temperature and to establish the deformational processes by which the salt reconsolidates. The experiments will be used to populate the database used in the reconsolidation model developed by Callahan (1999) which accounts for the effects of moisture through pressure solution and dislocation creep, with both terms dependent on effective stress to account for the effects of porosity. Mine-run salt from the Waste Isolation Pilot Program (WIPP) was first dried at 105 °C for a few days. Undeformed right-circular cylindrical sample assemblies of unconsolidated granular salt with an initial porosity of ~ 40%, nominally 10 cm in diameter and 17.5 cm in length, are jacketed in lead. Samples are placed in a pressure vessel and kept at test temperatures of 100, 175 or 250 °C; samples are vented to the atmosphere during the entire test procedure. At these test conditions the consolidating salt is always creeping, the creep rate increases with increasing temperature and stress and decreases as porosity decreases. In hydrostatic tests, confining pressure is increased to 20 MPa with periodic unload/reload loops to determine K. Volume strain increases with increasing temperature. In shear tests at 2.5 and 5 MPa confining pressure, after confining pressure is applied, the crushed salt is subjected to a differential stress, with periodic unload/reload loops to determine E and ν. At predetermined differential stress levels the stress is held constant and the salt consolidates. Displacement gages mounted on the samples show little lateral deformation until the samples reach a porosity of ~10%. Interestingly, vapor is vented in tests at 250°C and condenses at the vent port. Release of water is not observed in the lower two test temperatures. It is hypothesized that the water originates from fluid inclusions, which were made accessible by intragranular deformational processes including decrepitation. Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000.

Deep Geologic Nuclear Waste Disposal - No New Taxes - 12469

DOE Office of Scientific and Technical Information (OSTI.GOV)

Conca, James; Wright, Judith

2012-07-01

To some, the perceived inability of the United States to dispose of high-level nuclear waste justifies a moratorium on expansion of nuclear power in this country. Instead, it is more an example of how science yields to social pressure, even on a subject as technical as nuclear waste. Most of the problems, however, stem from confusion on the part of the public and their elected officials, not from a lack of scientific knowledge. We know where to put nuclear waste, how to put it there, how much it will cost, and how well it will work. And it's all aboutmore » the geology. The President's Blue Ribbon Commission on America's Nuclear Future has drafted a number of recommendations addressing nuclear energy and waste issues (BRC 2011) and three recommendations, in particular, have set the stage for a new strategy to dispose of high-level nuclear waste and to manage spent nuclear fuel in the United States: 1) interim storage for spent nuclear fuel, 2) resumption of the site selection process for a second repository, and 3) a quasi-government entity to execute the program and take control of the Nuclear Waste Fund in order to do so. The first two recommendations allow removal and storage of spent fuel from reactor sites to be used in the future, and allows permanent disposal of actual waste, while the third controls cost and administration. The Nuclear Waste Policy Act of 1982 (NPWA 1982) provides the second repository different waste criteria, retrievability, and schedule, so massive salt returns as the candidate formation of choice. The cost (in 2007 dollars) of disposing of 83,000 metric tons of heavy metal (MTHM) high-level waste (HLW) is about $ 83 billion (b) in volcanic tuff, $ 29 b in massive salt, and $ 77 b in crystalline rock. Only in salt is the annual revenue stream from the Nuclear Waste Fund more than sufficient to accomplish this program without additional taxes or rate hikes. The cost is determined primarily by the suitability of the geologic formation, i.e., how well it performs on its own for millions of years with little engineering assistance from humans. It is critical that the states most affected by this issue (WA, SC, ID, TN, NM and perhaps others) develop an independent multi-state agreement in order for a successful program to move forward. Federal approval would follow. Unknown to most, the United States has a successful operating deep permanent geologic nuclear repository for high and low activity waste, called the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. Its success results from several factors, including an optimal geologic and physio-graphic setting, a strong scientific basis, early regional community support, frequent interactions among stakeholders at all stages of the process, long-term commitment from the upper management of the U.S. Department of Energy (DOE) over several administrations, strong New Mexico State involvement and oversight, and constant environmental monitoring from before nuclear waste was first emplaced in the WIPP underground (in 1999) to the present. WIPP is located in the massive bedded salts of the Salado Formation, whose geological, physical, chemical, redox, thermal, and creep-closure properties make it an ideal formation for long-term disposal, long-term in this case being greater than 200 million years. These properties also mean minimal engineering requirements as the rock does most of the work of isolating the waste. WIPP has been operating for twelve years, and as of this writing, has disposed of over 80,000 m{sup 3} of nuclear weapons waste, called transuranic or TRU waste (>100 nCurie/g but <23 Curie/1000 cm{sup 3}) including some high activity waste from reprocessing of spent fuel from old weapons reactors. All nuclear waste of any type from any source can be disposed in this formation better, safer and cheaper than in any other geologic formation. At the same time, it is critical that we complete the Yucca Mountain license application review so as not to undermine the credibility of the Nuclear Regulatory Commission and the scientific community. (authors)« less

Salt Composition Derived from Veazey Composition by Thermodynamic Modeling and Predicted Composition of Drum Contents

DOE Office of Scientific and Technical Information (OSTI.GOV)

Weisbrod, Kirk Ryan; Veirs, Douglas Kirk; Funk, David John

This report describes the derivation of the salt composition from the Veazey salt stream analysis. It also provides an estimate of the proportions of the kitty litter, nitrate salt and neutralizer that was contained in drum 68660. While the actinide content of waste streams was judiciously followed in the 1980s in TA-55, no record of the salt composition could be found. Consequently, a salt waste stream produced from 1992 to 1994 and reported by Gerry Veazey provided the basis for this study. While chemical analysis of the waste stream was highly variable, an average analysis provided input to the Streammore » Analyzer software to calculate a composition for a concentrated solid nitrate salt and liquid waste stream. The calculation predicted the gas / condensed phase compositions as well as solid salt / saturated liquid compositions. The derived composition provides an estimate of the nitrate feedstream to WIPP for which kinetic measurements can be made. The ratio of salt to Swheat in drum 68660 contents was estimated through an overall mass balance on the parent and sibling drums. The RTR video provided independent confirmation concerning the volume of the mixture. The solid salt layer contains the majority of the salt at a ratio with Swheat that potentially could become exothermic.« less

Tritium Packages and 17th RH Canister Categories of Transuranic Waste Stored Below Ground within Area G

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hargis, Kenneth Marshall

A large wildfire called the Las Conchas Fire burned large areas near Los Alamos National Laboratory (LANL) in 2011 and heightened public concern and news media attention over transuranic (TRU) waste stored at LANL’s Technical Area 54 (TA-54) Area G waste management facility. The removal of TRU waste from Area G had been placed at a lower priority in budget decisions for environmental cleanup at LANL because TRU waste removal is not included in the March 2005 Compliance Order on Consent (Reference 1) that is the primary regulatory driver for environmental cleanup at LANL. The Consent Order is a settlementmore » agreement between LANL and the New Mexico Environment Department (NMED) that contains specific requirements and schedules for cleaning up historical contamination at the LANL site. After the Las Conchas Fire, discussions were held by the U.S. Department of Energy (DOE) with the NMED on accelerating TRU waste removal from LANL and disposing it at the Waste Isolation Pilot Plant (WIPP). This report summarizes available information on the origin, configuration, and composition of the waste containers within the Tritium Packages and 17th RH Canister categories; their physical and radiological characteristics; the results of the radioassays; and potential issues in retrieval and processing of the waste containers.« less

Mixed-layered bismuth-oxygen-iodine materials for capture and waste disposal of radioactive iodine

DOEpatents

Krumhansl, James L; Nenoff, Tina M

2013-02-26

Materials and methods of synthesizing mixed-layered bismuth oxy-iodine materials, which can be synthesized in the presence of aqueous radioactive iodine species found in caustic solutions (e.g. NaOH or KOH). This technology provides a one-step process for both iodine sequestration and storage from nuclear fuel cycles. It results in materials that will be durable for repository conditions much like those found in Waste Isolation Pilot Plant (WIPP) and estimated for Yucca Mountain (YMP). By controlled reactant concentrations, optimized compositions of these mixed-layered bismuth oxy-iodine inorganic materials are produced that have both a high iodine weight percentage and a low solubility in groundwater environments.

K-Basins Sludge Treatment and Packaging at the Hanford Site - 13585

DOE Office of Scientific and Technical Information (OSTI.GOV)

Fogwell, Thomas W.; Honeyman, James O.; Stegen, Gary

Highly radioactive sludge resulting from the storage of degraded spent nuclear fuel has been consolidated in Engineered Containers (ECs) in the 105-K West Storage Basin located on the Hanford site near the Columbia River in Washington State. CH2M Hill Plateau Remediation Company (CHPRC) is proceeding with a project to retrieve the sludge, place it in Sludge Transport and Storage Containers (STSCs) and store those filled containers within the T Plant Canyon facility on the Hanford Site Central Plateau (Phase 1). Retrieval and transfer of the sludge material will enable removal of the 105-K West Basin and allow remediation of themore » subsurface contamination plumes under the basin. The U.S. Department of Energy (DOE) plans to treat and dispose of this K Basins sludge (Phase 2) as Remote Handled Transuranic Waste (RH TRU) at the Waste Isolation Pilot Plant (WIPP) located in New Mexico. The K Basin sludge currently contains uranium metal which reacts with water present in the stored slurry, generating hydrogen and other byproducts. The established transportation and disposal requirements require the transformation of the K Basins sludge to a chemically stable, liquid-free, packaged waste form. The Treatment and Packaging Project includes removal of the containerised sludge from T Plant, the treatment of the sludge as required, and packaging of all the sludge into a form that is certifiable for transportation to and disposal at WIPP. Completion of this scope will require construction and operation of a Sludge Treatment and Packaging Facility (STPF), which could be either a completely new facility or a modification of an existing Hanford Site facility. A Technology Evaluation and Alternatives Analysis (TEAA) for the STP Phase 2 was completed in 2011. A Request for Technology Information (RFI) had been issued in October 2009 to solicit candidate technologies for use in Phase 2. The RFI also included a preliminary definition of Phase 2 functions and requirements. Potentially applicable technologies were identified through a commercial procurement process, technical workshops, and review of the numerous previous sludge treatment technology studies. The identified technology approaches were screened using the criteria established in the Decision Plan, and focused bench top feasibility testing was conducted. Engineering evaluations of the costs, schedules, and technical maturity were developed and evaluated. Recommendations were developed based on technical evaluations. The criteria used in the evaluation process were as follows: (1) Safety, (2) Regulatory/stakeholder acceptance, (3) Technical maturity, (4) Operability and maintainability, (5) Life cycle cost and schedule, (6) Potential for beneficial integration with ongoing STP-Phase 1 activities, and (7) Integration with Site-wide RH-TRU processing/packaging, planning, schedule, and approach. The TEAA recommended Warm Water Oxidation (WWO) as the baseline treatment technology and two risk reduction enhancement options for further consideration during development of the process - size reduction and chemical oxidation (Fenton's reagent). The enhancement options would potentially allow a useful reduction in the total operating time required to process the K Basins sludge. The U.S. Department of Energy's Richland Field Office (DOE-RL) has approved this recommended technical approach. The baseline process can be broken down into the following main process steps: (1) STSC transfer from T Plant to the Sludge Treatment and Packaging Facility (STPF). (2) Retrieval of sludge from the STSCs and transfer to the Receipt and Reaction Tank (RRT). (3) Preparation for immobilization by oxidation using heated water (i.e., WWO) for those batches that require it and concentration by evaporating water at about atmospheric pressure in the RRT. (4) Immobilization by using additives to eliminate free liquids and packaging of the treated sludge into drums. (5) Inspection and handling of the filled drums prior to transfer to a separate storage and shipping facility. (6) Handling of vapor, condensate, and other waste streams generated by the process. Each of these steps is discussed in the paper, together with the current state of progress in developing the technology and requirements for continued development. A schematic of the recommended baseline WWO treatment process is given below. (authors)« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Dewers, Thomas; Heath, Jason E.; Leigh, Christi D.

The nature of geologic disposal of nuclear waste in salt formations requires validated and verified two - phase flow models of transport of brine and gas through intact, damaged, and consolidating crushed salt. Such models exist in oth er realms of subsurface engineering for other lithologic classes (oil and gas, carbon sequestration etc. for clastics and carbonates) but have never been experimentally validated and parameterized for salt repository scenarios or performance assessment. Mo dels for waste release scenarios in salt back - fill require phenomenological expressions for capillary pressure and relative permeability that are expected to change with degree ofmore » consolidation, and require experimental measurement to parameterize and vali date. This report describes a preliminary assessment of the influence of consolidation (i.e. volume strain or porosity) on capillary entry pressure in two phase systems using mercury injection capillary pressure (MICP). This is to both determine the potent ial usefulness of the mercury intrusion porosimetry method, but also to enable a better experimental design for these tests. Salt consolidation experiments are performed using novel titanium oedometers, or uniaxial compression cells often used in soil mech anics, using sieved run - of - mine salt from the Waste Isolation Pilot Plant (WIPP) as starting material. Twelve tests are performed with various starting amounts of brine pore saturation, with axial stresses up to 6.2 MPa (%7E900 psi) and temperatures to 90 o C. This corresponds to UFD Work Package 15SN08180211 milestone "FY:15 Transport Properties of Run - of - Mine Salt Backfill - Unconsolidated to Consolidated". Samples exposed to uniaxial compression undergo time - dependent consolidation, or creep, to various deg rees. Creep volume strain - time relations obey simple log - time behavior through the range of porosities (%7E50 to 2% as measured); creep strain rate increases with temperature and applied stress as expected. Mercury porosimetry is used to determine characteri stic capillary pressure curves from a series of consolidation tests and show characteristic saturation - capillary pressure curves that follow the common van Genuchten (1978, 1980) formulation at low stresses. Higher capillary pressure data are suspect due t o the large potential for sample damage, including fluid inclusion decrepitation and pore collapse. Data are supportive of use of the Leverett "J" function (Leverett, 1941) to use for scaling characteristic curves at different degrees of consolidation, but better permeability determinations are needed to support this hypothesis. Recommendations for further and refined testing are made with the goal of developing a self - consistent set of constitutive laws for granular salt consolidation and multiphase (brin e - air) flow.« less

Revised Earthquake Catalog and Relocated Hypocenters Near Fluid Injection Wells and the Waste Isolation Pilot Plant (WIPP) in Southeastern New Mexico

NASA Astrophysics Data System (ADS)

Edel, S.; Bilek, S. L.; Garcia, K.

2014-12-01

Induced seismicity is a class of crustal earthquakes resulting from human activities such as surface and underground mining, impoundment of reservoirs, withdrawal of fluids and gas from the subsurface, and injection of fluids into underground cavities. Within the Permian basin in southeastern New Mexico lies an active area of oil and gas production, as well as the Waste Isolation Pilot Plant (WIPP), a geologic nuclear waste repository located just east of Carlsbad, NM. Small magnitude earthquakes have been recognized in the area for many years, recorded by a network of short period vertical component seismometers operated by New Mexico Tech. However, for robust comparisons between the seismicity patterns and the injection well locations and rates, improved locations and a more complete catalog over time are necessary. We present results of earthquake relocations for this area by using data from the 3-component broadband EarthScope Flexible Array SIEDCAR experiment that operated in the area between 2008-2011. Relocated event locations tighten into a small cluster of ~38 km2, approximately 10 km from the nearest injection wells. The majority of events occurred at 10-12 km depth, given depth residuals of 1.7-3.6 km. We also present a newly developed more complete catalog of events from this area by using a waveform cross-correlation algorithm and the relocated events as templates. This allows us to detect smaller magnitude events that were previously undetected with the short period network data. The updated earthquake catalog is compared with geologic maps and cross sections to identify possible fault locations. The catalog is also compared with available well data on fluid injection and production. Our preliminary results suggest no obvious connection between seismic moment release, fluid injection, or production given the available monthly industry data. We do see evidence in the geologic and well data of previously unidentified faults in the area.

Nuclear energy and radioactive waste disposal in the age of recycling

DOE Office of Scientific and Technical Information (OSTI.GOV)

Conca, James L.; Apted, Michael

2007-07-01

The magnitude of humanity's energy needs requires that we embrace a multitude of various energy sources and applications. For a variety of reasons, nuclear energy must be a major portion of the distribution, at least one third. The often-cited strategic hurdle to this approach is nuclear waste disposal. Present strategies concerning disposal of nuclear waste need to be changed if the world is to achieve both a sustainable energy distribution by 2040 and solve the largest environmental issue of the 21. century - global warming. It is hoped that ambitious proposals to replace fossil fuel power generation by alternatives willmore » drop the percentage of fossil fuel use substantially, but the absolute amount of fossil fuel produced electricity must be kept at or below its present 10 trillion kW-hrs/year. Unfortunately, the rapid growth in consumption to over 30 trillion kW-hrs/year by 2040, means that 20 trillion kW-hrs/yr of non-fossil fuel generated power has to come from other sources. If half of that comes from alternative non-nuclear, non-hydroelectric sources (an increase of 3000%), then nuclear still needs to increase by a factor of four worldwide to compensate. Many of the reasons nuclear energy did not expand after 1970 in North America (proliferation, capital costs, operational risks, waste disposal, and public fear) are no longer a problem. The WIPP site in New Mexico, an example of a solution to the nuclear waste disposal issue, and also to public fear, is an operating deep geologic nuclear waste repository in the massive bedded salt of the Salado Formation. WIPP has been operating for eight years, and as of this writing, has disposed of over 50,000 m{sup 3} of transuranic waste (>100 nCi/g but <23 Curie/liter) including high activity waste. The Salado Formation is an ideal host for any type of nuclear waste, especially waste from recycled spent fuel. (authors)« less

Geologic and well-construction data for the H-9 borehole complex near the proposed Waste Isolation Pilot Plant site, southeastern New Mexico

USGS Publications Warehouse

Drellack, S.L.; Wells, J.G.

1982-01-01

The H-9 complex, a group of three closely spaced boreholes, is located 5.5 miles south of the proposed Waste Isolation Pilot Plant (WIPP) site in east-central Eddy County, New Mexico. The holes were drilled during July, August, and September 1979 to obtain geologic and hydrologic data to better define the regional ground-water-flow system. The geologic data presented in this report are part of a site-characterization study for the possible storage of defense-associated radioactive wastes within salt beds of the Salado Formation of Permian age. The geologic data include detailed descriptions of cores, cuttings, and geophysical logs. Each borehole was designed to penetrate a distinct water-bearing zone: H-9a (total depth 559 feet) was completed just below the Magenta Dolomite Member of the Rustler Formation; H-9b (total depth 708 feet) was completed just below the Culebra Dolomite Member of the Rustler Formation; H-9c (total depth 816 feet) was completed below the Rustler Formation-Salado Formation contact. The geologic units penetrated in borehole H-9c are eolian sand of Holocene age (0-5 feet); the Gatuna Formation of Pleistocene age; (5-25 feet); and the Dewey Lake Red Beds (25-455 feet), the Rustler Formation (455.791 feet), and part of the Salado Formation (791-816 feet), all of Permian age. Three sections (494-501 feet, 615-625 feet, 692-712 feet) in the Rustler Formation penetrated by borehole H-9c are composed of remnant anhydrite (locally altered to gypsum) and clay and silt residue from the dissolution of much thicker seams of argillaceous and silty halite. This indicates that the eastward-moving dissolution within the Rustler Formation, found just to the west of the WIPP site, is present at the H-9 site. (USGS)

Waste-form development for conversion to portland cement at Los Alamos National Laboratory (LANL) Technical Area 55 (TA-55)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Veazey, G.W.; Schake, A.R.; Shalek, P.D.

1996-10-01

The process used at TA-55 to cement transuranic (TRU) waste has experienced several problems with the gypsum-based cement currently being used. Specifically, the waste form could not reliably pass the Waste Isolation Pilot Plant (WIPP) prohibition for free liquid and the Environmental Protection Agency (EPA)-Toxicity Characteristic Leaching Procedure (TCLP) standard for chromium. This report describes the project to develop a portland cement-based waste form that ensures compliance to these standards, as well as other performance standards consisting of homogeneous mixing, moderate hydration temperature, timely initial set, and structural durability. Testing was conducted using the two most common waste streams requiringmore » cementation as of February 1994, lean residue (LR)- and oxalate filtrate (OX)-based evaporator bottoms (EV). A formulation with a pH of 10.3 to 12.1 and a minimum cement-to-liquid (C/L) ratio of 0.80 kg/l for OX-based EV and 0.94 kg/L for LR-based EV was found to pass the performance standards chosen for this project. The implementation of the portland process should result in a yearly cost savings for raw materials of approximately $27,000 over the gypsum process.« less

Summary Report of Laboratory Testing to Establish the Effectiveness of Proposed Treatment Methods for Unremediated and Remediated Nitrate Salt Waste Streams

DOE Office of Scientific and Technical Information (OSTI.GOV)

Anast, Kurt Roy; Funk, David John

The inadvertent creation of transuranic waste carrying hazardous waste codes D001 and D002 requires the treatment of the material to eliminate the hazardous characteristics and allow its eventual shipment and disposal at the Waste Isolation Pilot Plant (WIPP). This report documents the effectiveness of two treatment methods proposed to stabilize both the unremediated and remediated nitrate salt waste streams (UNS and RNS, respectively). The two technologies include the addition of zeolite (with and without the addition of water as a processing aid) and cementation. Surrogates were developed to evaluate both the solid and liquid fractions expected from parent waste containers,more » and both the solid and liquid fractions were tested. Both technologies are shown to be effective at eliminating the characteristic of ignitability (D001), and the addition of zeolite was determined to be effective at eliminating corrosivity (D002), with the preferred option1 of zeolite addition currently planned for implementation at the Waste Characterization, Reduction, and Repackaging Facility. During the course of this work, we established the need to evaluate and demonstrate the effectiveness of the proposed remedy for debris material, if required. The evaluation determined that Wypalls absorbed with saturated nitrate salt solutions exhibit the ignitability characteristic (all other expected debris is not classified as ignitable). Follow-on studies will be developed to demonstrate the effectiveness of stabilization for ignitable Wypall debris. Finally, liquid surrogates containing saturated nitrate salts did not exhibit the characteristic of ignitability in their pure form (those neutralized with Kolorsafe and mixed with sWheat did exhibit D001). As a result, additional nitrate salt solutions (those exhibiting the oxidizer characteristic) will be tested to demonstrate the effectiveness of the remedy.« less

Savannah River Site Operating Experience with Transuranic (TRU) Waste Retrieval

DOE Office of Scientific and Technical Information (OSTI.GOV)

Stone, K.A.; Milner, T.N.

2006-07-01

Drums of TRU Waste have been stored at the Savannah River Site (SRS) on concrete pads from the 1970's through the 1980's. These drums were subsequently covered with tarpaulins and then mounded over with dirt. Between 1996 and 2000 SRS ran a successful retrieval campaign and removed some 8,800 drums, which were then available for venting and characterization for WIPP disposal. Additionally, a number of TRU Waste drums, which were higher in activity, were stored in concrete culverts, as required by the Safety Analysis for the Facility. Retrieval of drums from these culverts has been ongoing since 2002. This papermore » will describe the operating experience and lessons learned from the SRS retrieval activities. (authors)« less

Mixed-layered bismuth--oxygen--iodine materials for capture and waste disposal of radioactive iodine

DOE Office of Scientific and Technical Information (OSTI.GOV)

Krumhansl, James L; Nenoff, Tina M

2015-01-06

Materials and methods of synthesizing mixed-layered bismuth oxy-iodine materials, which can be synthesized in the presence of aqueous radioactive iodine species found in caustic solutions (e.g. NaOH or KOH). This technology provides a one-step process for both iodine sequestration and storage from nuclear fuel cycles. It results in materials that will be durable for repository conditions much like those found in Waste Isolation Pilot Plant (WIPP) and estimated for Yucca Mountain (YMP). By controlled reactant concentrations, optimized compositions of these mixed-layered bismuth oxy-iodine inorganic materials are produced that have both a high iodine weight percentage and a low solubility inmore » groundwater environments.« less

Neutron-induced reactions in the hohlraum to study reaction in flight neutrons

DOE Office of Scientific and Technical Information (OSTI.GOV)

Boswell, M. S.; Elliott, S. R.; Tybo, J.

2013-04-19

We are currently developing the physics necessary to measure the Reaction In Flight (RIF) neutron flux from a NIF capsule. A measurement of the RIF neutron flux from a NIF capsule could be used to deduce the stopping power in the cold fuel of the NIF capsule. A foil irradiated at the Omega laser at LLE was counted at the LANL low-background counting facility at WIPP. The estimated production rate of {sup 195}Au was just below our experimental sensitivity. We have made several improvements to our counting facility in recent months. These improvements are designed to increase our sensitivity, andmore » include installing two new low-background detectors, and taking steps to reduce noise in the signals.« less

Benchmarking transportation logistics practices for effective system planning

DOE Office of Scientific and Technical Information (OSTI.GOV)

Thrower, A.W.; Dravo, A.N.; Keister, M.

2007-07-01

This paper presents preliminary findings of an Office of Civilian Radioactive Waste Management (OCRWM) benchmarking project to identify best practices for logistics enterprises. The results will help OCRWM's Office of Logistics Management (OLM) design and implement a system to move spent nuclear fuel (SNF) and high-level radioactive waste (HLW) to the Yucca Mountain repository for disposal when that facility is licensed and built. This report suggests topics for additional study. The project team looked at three Federal radioactive material logistics operations that are widely viewed to be successful: (1) the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico; (2)more » the Naval Nuclear Propulsion Program (NNPP); and (3) domestic and foreign research reactor (FRR) SNF acceptance programs. (authors)« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Xu, Hongwu; Guo, Xiaofeng; Bai, Jianming

As an accessory mineral in marine evaporites, polyhalite, K 2MgCa 2(SO 4) 4·2H 2O, coexists with halite (NaCl) in salt formations, which have been considered as potential repositories for permanent storage of high-level nuclear wastes. However, because of the heat generated by radioactive decays in the wastes, polyhalite may dehydrate, and the released water will dissolve its neighboring salt, potentially affecting the repository integrity. Thus, studying the thermal behavior of polyhalite is important. In this paper, a polyhalite sample containing a small amount of halite was collected from the Salado formation at the WIPP site in Carlsbad, New Mexico. Tomore » determine its thermal behavior, in situ high-temperature synchrotron X-ray diffraction was conducted from room temperature to 1066 K with the sample powders sealed in a silica-glass capillary. At about 506 K, polyhalite started to decompose into water vapor, anhydrite (CaSO 4) and two langbeinite-type phases, K 2Ca x Mg 2-x (SO 4) 3, with different Ca/Mg ratios. XRD peaks of the minor halite disappeared, presumably due to its dissolution by water vapor. With further increasing temperature, the two langbeinite solid solution phases displayed complex variations in crystallinity, composition and their molar ratio and then were combined into the single-phase triple salt, K 2CaMg(SO 4) 3, at ~919 K. Rietveld analyses of the XRD data allowed determination of structural parameters of polyhalite and its decomposed anhydrite and langbeinite phases as a function of temperature. Finally, from the results, the thermal expansion coefficients of these phases have been derived, and the structural mechanisms of their thermal behavior been discussed.« less

Thermal behavior of polyhalite: a high-temperature synchrotron XRD study

DOE PAGES

Xu, Hongwu; Guo, Xiaofeng; Bai, Jianming

2016-09-17

As an accessory mineral in marine evaporites, polyhalite, K 2MgCa 2(SO 4) 4·2H 2O, coexists with halite (NaCl) in salt formations, which have been considered as potential repositories for permanent storage of high-level nuclear wastes. However, because of the heat generated by radioactive decays in the wastes, polyhalite may dehydrate, and the released water will dissolve its neighboring salt, potentially affecting the repository integrity. Thus, studying the thermal behavior of polyhalite is important. In this paper, a polyhalite sample containing a small amount of halite was collected from the Salado formation at the WIPP site in Carlsbad, New Mexico. Tomore » determine its thermal behavior, in situ high-temperature synchrotron X-ray diffraction was conducted from room temperature to 1066 K with the sample powders sealed in a silica-glass capillary. At about 506 K, polyhalite started to decompose into water vapor, anhydrite (CaSO 4) and two langbeinite-type phases, K 2Ca x Mg 2-x (SO 4) 3, with different Ca/Mg ratios. XRD peaks of the minor halite disappeared, presumably due to its dissolution by water vapor. With further increasing temperature, the two langbeinite solid solution phases displayed complex variations in crystallinity, composition and their molar ratio and then were combined into the single-phase triple salt, K 2CaMg(SO 4) 3, at ~919 K. Rietveld analyses of the XRD data allowed determination of structural parameters of polyhalite and its decomposed anhydrite and langbeinite phases as a function of temperature. Finally, from the results, the thermal expansion coefficients of these phases have been derived, and the structural mechanisms of their thermal behavior been discussed.« less

The Direct Path To WIPP - 12471

DOE Office of Scientific and Technical Information (OSTI.GOV)

Spoerner, M.T.; Burger, M.J.; Garcia, J.

2012-07-01

Sandia National Laboratories/New Mexico (SNL/NM), designated as a small quantity site (SQS) by the National TRU Program (NTP), generated contact-handled (CH) and remote-handled (RH) transuranic (TRU) waste primarily from the decontamination and clean-out of glove boxes at the Hot Cell Facility (HCF) at Technical Area (TA) V. All of the waste required repackaging, with the CH TRU waste being repackaged from late 2007 through 2011. Three shipments of CH were completed in October 2011, which de-inventoried SNL/NM's legacy TRU waste. In FY11, RH TRU waste was repackaged at the Auxiliary Hot Cell Facility (AHCF) located in TAV with the supportmore » of the Central Characterization Project (CCP). The waste was originally packaged in SNL/NM fabricated casks, cement or lead-lined 55-gallon drums, or 30-gallon drums. The AHCF is a small hot cell, with access only through a roof port which presented challenges for inserting and removing waste from the hot cell. The CCP provided visual examination operators (VEOs) to observe and document each waste item repackaged, removal of prohibited items, and radiological sampling. Dose-to-Curie measurements were calculated by CCP after a radiological report was prepared using scaling factors determined by the analysis of swipe samples. Finally, headspace gas samples were taken and sent to the Advanced Mixed Waste Treatment Project (AMWTP) for analysis. Despite the challenges, the RH waste is on track to be shipped to WIPP in early FY12. The processes used and procedures developed to conduct the repackaging operations, the issues identified and mitigated were challenging but the cooperation between SNL/NM and the Central Characterization Program (CCP) enabled SNL/NM to complete the repackaging and support the characterization and shipment. An inventory list, identification of the campaigns, discussion of the challenges and mitigations, and the final loading of the RH 72-B casks at TA-V for direct shipment to the Waste Isolation Pilot Plant (WIPP) will be discussed. Lessons learned from the RH campaigns are: - Some containers that were originally identified as HC-3 have been re-evaluated and became < HC-3 due to the conservative estimates made by the original generators - Operators at the AHCF were not accustomed to the detail required by the VE operators. However, they worked well together and the repackaging was completed ahead of schedule. - The AK was not always accurate as was demonstrated by the solid waste found in the drum during the first visit by EPA. That waste has since been determined to be low-level. - Two drums originally thought to be RH turned out to be CH and arrangement for RTR had to be made quickly. - Six of the original RH repacked drums became low level. - Lessons learned from the CH campaigns were helpful in avoiding many issues. The RH repackaging effort has been a success due to the expertise of the AHCF operators, supervisor, and manager, the conscientious attention to detail of the CCP VE operators, the experience of the CCP DTC and headspace gas sampling staff, and the guidance and support from CCP and CBFO. Sometimes schedules had to be adjusted, processes updated, and issues discussed, but the communication between CCP and SNL/NM was good. SNL/NM hopes to have the legacy RH TRU waste shipped off-site by early 2012. (authors)« less

Determination of the Porosity Surfaces of the Disposal Room Containing Various Waste Inventories for WIPP PA

DOE Office of Scientific and Technical Information (OSTI.GOV)

Park, Byoung Yoon; Hansen, Francis D.

2005-07-01

This report develops a series of porosity surfaces for the Waste Isolation Pilot Plant. The concept of a porosity surface was developed for performance assessment and comprises calculation of room closure as salt creep processes are mitigated by gas generation and back stress created by the waste packages within the rooms. The physical and mechanical characteristics of the waste packaging that has already been disposed--such as the pipe overpack--and new waste packaging--such as the advanced mixed waste compaction--are appreciably different than the waste form upon which the original compliance was based and approved. This report provides structural analyses of roommore » closure with various waste inventories. All of the underlying assumptions pertaining to the original compliance certification including the same finite element code are implemented; only the material parameters describing the more robust waste packages are changed from the certified baseline. As modeled, the more rigid waste tends to hold open the rooms and create relatively more void space in the underground than identical calculations run on the standard waste packages, which underpin the compliance certification. The several porosity surfaces quantified within this report provide possible ranges of pressure and porosity for performance assessment analyses.3 Intentionally blank4 AcknowledgementsThis research is funded by WIPP programs administered by the U.S. Department of Energy. The authors would like to acknowledge the valuable contributions to this work provided by others. Dr. Joshua S. Stein helped explain the hand off between these finite element porosity surfaces and implementation in the performance calculations. Dr. Leo L. Van Sambeek of RESPEC Inc. helped us understand the concepts of room closure under the circumstances created by a rigid waste inventory. Dr. T. William Thompson and Tom W. Pfeifle provided technical review and Mario J. Chavez provided a Quality Assurance review. The paper has been improved by these individuals.Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy under Contract DE-AC04-94Al850005 Intentionally Blank6« less

Solubility Model for Ferrous Iron Hydroxide, Hibbingite, Siderite, and Chukanovite in High Saline Solutions of Sodium Chloride, Sodium Sulfate, and Sodium Carbonate

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kim, Sungtae; Marrs, Cassandra; Nemer, Martin

Here, a solubility model is presented for ferrous iron hydroxide (Fe(OH) 2(s)), hibbingite (Fe 2Cl(OH) 3(s)), siderite (FeCO 3(s)), and chukanovite (Fe 2CO 3(OH) 2(s)). The Pitzer activity coefficient equation was utilized in developing the model to account for the excess free energies of aqueous species in the background solutions of high ionic strength. Solubility limiting minerals were analyzed before and after experiments using X-ray diffraction. Formation of Fe(OH) 2(s) was observed in the experiments that were initiated with Fe 2Cl(OH) 3(s) in Na 2SO 4 solution. Coexistence of siderite and chukanovite was observed in the experiments in Na 2COmore » 3 + NaCl solutions. Two equilibrium constants that had been reported by us for the dissolution of Fe(OH) 2(s) and Fe 2Cl(OH) 3(s) (Nemer et al.) were rederived in this paper, using newer thermodynamic data selected from the literature to maintain internal consistency of the series of our data analyses in preparation, including this paper. Three additional equilibrium constants for the following reactions were determined in this paper: dissolution of siderite and chukanovite and dissociation of the aqueous species Fe(CO 3) 2 –2. Five Pitzer interaction parameters were derived in this paper: β (0), β (1), and C φ parameters for the species pair Fe +2/SO 4 –2; β (0) and β (1) parameters for the species pair Na+/Fe(CO3)2–2. Our model predicts that, among the four inorganic ferrous iron minerals, siderite is the stable mineral in two WIPP-related brines (WIPP: Waste Isolation Pilot Plant), i.e., GWB and ERDA6 (Brush and Domski), and the electrochemical equilibrium between elemental iron and siderite provides a low oxygen fugacity (10 –91.2 atm) that can keep the actinides at their lowest oxidation states. (Nemer et al., Brush and Domski; references numbered 1 and 2 in the main text).« less

Solubility Model for Ferrous Iron Hydroxide, Hibbingite, Siderite, and Chukanovite in High Saline Solutions of Sodium Chloride, Sodium Sulfate, and Sodium Carbonate

DOE PAGES

Kim, Sungtae; Marrs, Cassandra; Nemer, Martin; ...

2017-11-20

Here, a solubility model is presented for ferrous iron hydroxide (Fe(OH) 2(s)), hibbingite (Fe 2Cl(OH) 3(s)), siderite (FeCO 3(s)), and chukanovite (Fe 2CO 3(OH) 2(s)). The Pitzer activity coefficient equation was utilized in developing the model to account for the excess free energies of aqueous species in the background solutions of high ionic strength. Solubility limiting minerals were analyzed before and after experiments using X-ray diffraction. Formation of Fe(OH) 2(s) was observed in the experiments that were initiated with Fe 2Cl(OH) 3(s) in Na 2SO 4 solution. Coexistence of siderite and chukanovite was observed in the experiments in Na 2COmore » 3 + NaCl solutions. Two equilibrium constants that had been reported by us for the dissolution of Fe(OH) 2(s) and Fe 2Cl(OH) 3(s) (Nemer et al.) were rederived in this paper, using newer thermodynamic data selected from the literature to maintain internal consistency of the series of our data analyses in preparation, including this paper. Three additional equilibrium constants for the following reactions were determined in this paper: dissolution of siderite and chukanovite and dissociation of the aqueous species Fe(CO 3) 2 –2. Five Pitzer interaction parameters were derived in this paper: β (0), β (1), and C φ parameters for the species pair Fe +2/SO 4 –2; β (0) and β (1) parameters for the species pair Na+/Fe(CO3)2–2. Our model predicts that, among the four inorganic ferrous iron minerals, siderite is the stable mineral in two WIPP-related brines (WIPP: Waste Isolation Pilot Plant), i.e., GWB and ERDA6 (Brush and Domski), and the electrochemical equilibrium between elemental iron and siderite provides a low oxygen fugacity (10 –91.2 atm) that can keep the actinides at their lowest oxidation states. (Nemer et al., Brush and Domski; references numbered 1 and 2 in the main text).« less

A New Concept: Use of Negotiations in the Hazardous Waste Facility Permitting Process in New Mexico

DOE Office of Scientific and Technical Information (OSTI.GOV)

Johnson, G.J.; Rose, W.M.; Domenici, P.V.

This paper describes a unique negotiation process leading to authorization of the U.S. Department of Energy (DOE) to manage and dispose remote-handled (RH) transuranic (TRU) mixed wastes at the Waste Isolation Pilot Plant (WIPP). The negotiation process involved multiple entities and individuals brought together under authority of the New Mexico Environment Department (NMED) to discuss and resolve technical and facility operational issues flowing from an NMED-issued hazardous waste facility Draft Permit. The novel negotiation process resulted in numerous substantive changes to the Draft Permit, which were ultimately memorialised in a 'Draft Permit as Changed'. This paper discusses various aspects ofmore » the negotiation process, including events leading to the negotiations, regulatory basis for the negotiations, negotiation participants, and benefits of the process. (authors)« less

The cement solidification systems at LANL

DOE Office of Scientific and Technical Information (OSTI.GOV)

Veazey, G.W.

1990-01-01

There are two major cement solidification systems at Los Alamos National Laboratory. Both are focused primarily around treating waste from the evaporator at TA-55, the Plutonium Processing Facility. The evaporator receives the liquid waste stream from TA-55's nitric acid-based, aqueous-processing operations and concentrates the majority of the radionuclides in the evaporator bottoms solution. This is sent to the TA-55 cementation system. The evaporator distillate is sent to the TA-50 facility, where the radionuclides are precipitated and then cemented. Both systems treat TRU-level waste, and so are operated according to the criteria for WIPP-destined waste, but they differ in both cementmore » type and mixing method. The TA-55 systems uses Envirostone, a gypsum-based cement and in-drum prop mixing; the TA-50 systems uses Portland cement and drum tumbling for mixing.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Neill, Robert H.

Since all efforts to date to dispose of HLW in the US have been unsuccessful, the following specific actions need to be taken if we are serious about such disposal: - The requirement in the EPA environmental radiation protection standards to predict the behavior of these unwanted residuals for one million years is meaningless. The Standards must be revisited. - Characterize two sites. There are myriad ways a site can be found to be unacceptable. Additionally, the existing HLW inventory requires a second repository. - Congress should specify incentives to states under consideration for a site. Perhaps 5% of totalmore » cost would be appropriate. - An independent technical review group should be established in such states to evaluate a proposed repository similar to the New Mexico Environmental Evaluation Group (EEG) for the WIPP Project because the state's interests are not necessarily the same as DOE's. - Acceptance or rejection of a proposed site should be based on technical issues, not social ones. Professionals in this field should present papers identifying the merits of HLW disposal in their own state. The scarcity of such research suggests Not In My Back Yard (NIMBY) syndrome. - Medical diagnostic ionizing radiation exposure to the US public is now 8,000 times greater than radiation exposure from nuclear energy. People accept this believing the benefits outweigh any risks. A major effort needs to focus on both benefits as well as risks of radioactive waste disposal. - DOE needs to announce preferences of host rock formations, incentives for states, and potential consequences should we fail to act. (author)« less

High-Temperature Oxidation of Plutonium Surrogate Metals and Alloys

DOE Office of Scientific and Technical Information (OSTI.GOV)

Sparks, Joshua C.; Krantz, Kelsie E.; Christian, Jonathan H.

The Plutonium Management and Disposition Agreement (PMDA) is a nuclear non-proliferation agreement designed to remove 34 tons of weapons-grade plutonium from Russia and the United States. While several removal options have been proposed since the agreement was first signed in 2000, processing the weapons-grade plutonium to mixed-oxide (MOX) fuel has remained the leading candidate for achieving the goals of the PMDA. However, the MOX program has received its share of criticisms, which causes its future to be uncertain. One alternative pathway for plutonium disposition would involve oxidizing the metal followed by impurity down blending and burial in the Waste Isolationmore » Pilot Plant (WIPP) in Carlsbad, New Mexico. This pathway was investigated by use of a hybrid microwave and a muffle furnace with Fe and Al as surrogate materials. Oxidation occurred similarly in the microwave and muffle furnace; however, the microwave process time was significantly faster.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hurd, J.R.

The active-passive shuffler installed and certified a few years ago in Los Alamos National Laboratory`s plutonium facility has now been calibrated for different matrices to measure Waste Isolation Pilot Plant (WIPP)-destined transuranic (TRU)-waste. Little or no data presently exist for these types of measurements in plant environments where there may be sudden large changes in the neutron background radiation which causes distortions in the results. Measurements and analyses of twenty-two 55-gallon drums, consisting of mixtures of varying quantities of uranium and plutonium, have been recently completed at the plutonium facility. The calibration and measurement techniques, including the method used tomore » separate out the plutonium component, will be presented and discussed. Particular attention will be directed to those problems identified as arising from the plant environment. The results of studies to quantify the distortion effects in the data will be presented. Various solution scenarios will be indicated, along with those adopted here.« less

Discussion of the paper ``the use of conditional simulation in nuclear waste site performance assessment,`` by Carol A. Gotway

DOE Office of Scientific and Technical Information (OSTI.GOV)

Gilbert, R.O.; Doctor, P.G.

1993-08-01

First, we applaud Dr. Gotway for seeking via her paper to expose a wider audience of statisticians to the many interesting and challenging modeling and statistical problems in the environmental area. This well-written paper effective explains the WIPP and the context of the analysis. Dr. Gotway`s paper describes a geostatistical conditional simulation approach combined with deterministic modeling to estimate the cumulative distribution function (cdf) of groundwater travel time (GWTT), information that is needed for estimating the cumulative release of nuclear waste from the repository. We begin our discussion with comments and questions on modeling aspects of Dr. Gotway`s paper. Thenmore » we discuss uncertainty and sensitivity analyses and some of the problems inherent with implementing those techniques including correlations, elicitation of expert opinion, and planning to achieve specified Data Quality Objectives (DQOs).« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Singledecker, Steven John

The purpose of this document is to describe the waste stream from Z-Pinch Residual Waste Project that due to worker safety concerns and operational efficiency is a candidate for blending Transuranic and low level waste together and can be safely packaged as low-level waste consistent with DOE Order 435.1 requirements and NRC guidance 10 CFR 61.42. This waste stream consists of the Pu-ICE post-shot containment systems, including plutonium targets, generated from the Z Machine experiments requested by LANL and conducted by SNL/NM. In the past, this TRU waste was shipped back to LANL after Sandia sends the TRU data packagemore » to LANL to certify the characterization (by CCP), transport and disposition at WIPP (CBFO) per LANL MOU-0066. The Low Level Waste is managed, characterized, shipped and disposed of at NNSS by SNL/NM per Sandia MOU # 11-S-560.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Spangler, Lorenz R.; Most, Wm. A.

The Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit (HWFP) limits the allowable emissions of volatile organic compounds (VOCs) from contact handled (CH) transuranic (TRU) waste. The environmental Performance standard within the HWFP, Module IV, Table IV.D.1, prescribes the allowed VOC emissions from the waste to ensure protection of human health and the environment. Compliance with the performance standard to ensure control of VOC emissions is based on VOC concentrations and monitoring in the underground. One of the mechanisms used to ensure compliance with the emissions standards is measuring the VOC concentration in the headspace gas of waste containersmore » prior to disposal. Headspace gas sampling and analysis is the waste characterization activity used to determine the concentration of VOCs in the headspace of waste containers. In addition to being used to demonstrate compliance with the emissions standards of Module IV, Table IV.D.1, the results of the headspace gas sampling and analysis are used to confirm the hazardous wastes identified in the acceptable knowledge (AK) process. Headspace gas sampling and analysis has been an ongoing part of the CH TRU waste characterization program and therefore data are now available concerning its use and applicability. The information from approved Waste Stream Profile Forms (WSPFs) and the headspace gas sampling and analysis results for over 16,000 containers of CH TRU waste were considered as part of this study. The headspace gas sampling and analysis results are based on data from the WIPP Waste Information System (WWIS). These results were evaluated to determine the usefulness of headspace gas sampling and analysis for confirming AK information. The evaluation shows that the reliability of using the results of headspace gas sampling and analysis to confirm AK information can be grouped by mixed and non-mixed waste streams. In general, for mixed waste streams due to VOCs (i.e., carrying VOC-related hazardous waste numbers), there is no reliable comparison that can be made for the detection of a particular target analyte and its associated hazardous waste number(s) based on the AK information on a compound by compound basis. However, for non-mixed waste streams, the results of headspace gas sampling and analysis show a better correlation to the AK information.« less

Use of acceptable knowledge to demonstrate TRAMPAC compliance

DOE Office of Scientific and Technical Information (OSTI.GOV)

Whitworth, J.; Becker, B.; Guerin, D.

2004-01-01

Recently, Los Alamos National Laboratory-Carlsbad Operations (LANL-CO) has supported the Central Characterization Project (CCP) managed by the U.S. Department of Energy (DOE) in the shipment of transuranic (TRU) waste from various small-quantity TRU waste generators to hub sites or other DOE sites in TRUPACT-II shipping containers. This support has involved using acceptable knowledge (AK) to demonstrate compliance with various requirements of Revision 19 of the TRUPACT-II Authorized Methods of Payload Compliance (TRAMPAC). LANL-CO has worked to facilitate TRUPACT-II shipments from the University of Missouri Research Reactor (MURR) and Lovelace Respiratory Research Institute (LRRI) to Argonne National Laboratory-East (ANL-E) and Losmore » Alamos National Laboratory (LANL), respectively. The latter two sites have TRU waste certification programs approved to ship waste to the Waste Isolation Pilot Plant (WIPP) for disposal. In each case, AK was used to satisfy the necessary information to ship the waste to other DOE facilities. For the purposes of intersite shipment, AK provided data to WIPP Waste Information System (WWIS) transportation modules to ensure that required information was obtained prior to TRUPACT-II shipments. The WWIS modules were used for the intersite shipments, not to enter certification data into WWIS, but rather to take advantage of a validated system to ensure that the containers to be shipped were compliant with TRAMPAC requirements, particularly in the evaluation of quantitative criteria. LANL-CO also assisted with a TRAMPAC compliance demonstration for homogeneous waste containers shipped in TRUPACT-II containers from ANL-E to Idaho National Engineering and Environmental Laboratory (INEEL) for the purpose of core sampling. The basis for the TRAMPAC compliance determinations was AK regarding radiological composition, chemical composition, TRU waste container packaging, and absence of prohibited items. Also, even in the case where AK is not used to fully demonstrate TRAMPAC compliance, it may be used to identify problem areas for shippability of different waste streams. An example is the case of Pu-238-contaminated waste from the Savannah River Site that had a low probability of meeting decay heat limits and aspiration times due to several factors including large numbers of confinement layers. This paper will outline 17 TRAMPAC compliance criteria assessed and the types of information used to show compliance with all criteria other than dose rate and container weight, which are normally easily measured at load preparation.« less

Analysis of Measurement Error and Estimator Shape in Three-Point Hydraulic Gradient Estimators

NASA Astrophysics Data System (ADS)

McKenna, S. A.; Wahi, A. K.

2003-12-01

Three spatially separated measurements of head provide a means of estimating the magnitude and orientation of the hydraulic gradient. Previous work with three-point estimators has focused on the effect of the size (area) of the three-point estimator and measurement error on the final estimates of the gradient magnitude and orientation in laboratory and field studies (Mizell, 1980; Silliman and Frost, 1995; Silliman and Mantz, 2000; Ruskauff and Rumbaugh, 1996). However, a systematic analysis of the combined effects of measurement error, estimator shape and estimator orientation relative to the gradient orientation has not previously been conducted. Monte Carlo simulation with an underlying assumption of a homogeneous transmissivity field is used to examine the effects of uncorrelated measurement error on a series of eleven different three-point estimators having the same size but different shapes as a function of the orientation of the true gradient. Results show that the variance in the estimate of both the magnitude and the orientation increase linearly with the increase in measurement error in agreement with the results of stochastic theory for estimators that are small relative to the correlation length of transmissivity (Mizell, 1980). Three-point estimator shapes with base to height ratios between 0.5 and 5.0 provide accurate estimates of magnitude and orientation across all orientations of the true gradient. As an example, these results are applied to data collected from a monitoring network of 25 wells at the WIPP site during two different time periods. The simulation results are used to reduce the set of all possible combinations of three wells to those combinations with acceptable measurement errors relative to the amount of head drop across the estimator and base to height ratios between 0.5 and 5.0. These limitations reduce the set of all possible well combinations by 98 percent and show that size alone as defined by triangle area is not a valid discriminator of whether or not the estimator provides accurate estimates of the gradient magnitude and orientation. This research was funded by WIPP programs administered by the U.S Department of Energy. Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000.

Chemistry of transuranium elements in salt-base repository

DOE Office of Scientific and Technical Information (OSTI.GOV)

Borkowski, Marian; Reed, Donald T; Lucchini, Jean - Francois

2010-12-02

The mobility and potential release of actinides into the accessible environment continues to be the key performance assessment concern of nuclear repositories. Actinide, in particular plutonium speciation under the wide range of conditions that can exist in the subsurface is complex and depends strongly on the coupled effects of redox conditions, inorganic/organic complexation, and the extent/nature of aggregation. Understanding the key factors that define the potential for actinide migration is, in this context, an essential and critical part of making and sustaining a licensing case for a nuclear repository. Herein we report on recent progress in a concurrent modeling andmore » experimental study to determine the speciation of plutonium, uranium and americium in high ionic strength Na-CI-Mg brines. This is being done as part of the ongomg recertification effort m the Waste Isolation Pilot Plant (WIPP). The oxidation-state specific solubility of actinides were established in brine as function of pC{sub H+}, brine composition and the presence and absence of organic chelating agents and carbonate. An oxidation-state invariant analog approach using Nd{sup 3+} and Th{sup 4+} was used for An{sup 3+} and An{sup 4+} respectively. These results show that organic ligands and hydrolysis are key factors for An(III) solubility, hydrolysis at pC{sub H+} above 8 is predominate for An(IV) and carbonates are the key factor for U(VI) solubility. The effect of high ionic strength and brine components measured in absence of carbonates leads to measurable increased in overall solubility over analogous low ionic strength groundwater. Less is known about the bioreduction of actinides by halo-tolerant microorganisms, but there is now evidence that bioreduction does occur and is analogous, in many ways, to what occurs with soil bacteria. Results of solubility studies that focus on Pitzer parameter corrections, new species (e.g. borate complexation), and the thermodynamic parameters for modeling are discussed.« less

Geomechanical Simulation of Bayou Choctaw Strategic Petroleum Reserve - Model Calibration.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Park, Byoung

2017-02-01

A finite element numerical analysis model has been constructed that consists of a realistic mesh capturing the geometries of Bayou Choctaw (BC) Strategic Petroleum Reserve (SPR) site and multi - mechanism deformation ( M - D ) salt constitutive model using the daily data of actual wellhead pressure and oil - brine interface. The salt creep rate is not uniform in the salt dome, and the creep test data for BC salt is limited. Therefore, the model calibration is necessary to simulate the geomechanical behavior of the salt dome. The cavern volumetric closures of SPR caverns calculated from CAVEMAN aremore » used for the field baseline measurement. The structure factor, A 2 , and transient strain limit factor, K 0 , in the M - D constitutive model are used for the calibration. The A 2 value obtained experimentally from the BC salt and K 0 value of Waste Isolation Pilot Plant (WIPP) salt are used for the baseline values. T o adjust the magnitude of A 2 and K 0 , multiplication factors A2F and K0F are defined, respectively. The A2F and K0F values of the salt dome and salt drawdown skins surrounding each SPR cavern have been determined through a number of back fitting analyses. The cavern volumetric closures calculated from this model correspond to the predictions from CAVEMAN for six SPR caverns. Therefore, this model is able to predict past and future geomechanical behaviors of the salt dome, caverns, caprock , and interbed layers. The geological concerns issued in the BC site will be explained from this model in a follow - up report .« less

Status and Prospects for the EXO-200 and nEXO Experiments

NASA Astrophysics Data System (ADS)

Yang, Liang; ">EXO-200, Status of EXO-200

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ackerman, Nicole; /SLAC

2011-12-06

EXO-200 is the first phase of the Enriched Xenon Observatory (EXO) experiment, which searches for neutrinoless double beta decay in {sup 136}Xe to measure the mass and probe the Majorana nature of the neutrino. EXO-200 consists of 200 kg of liquid Xe enriched to 80% in {sup 136}Xe in an ultra-low background TPC. Energy resolution is enhanced through the simultaneous collection of scintillation light using Large Area Avalanche Photodiodes (LAAPD's) and ionization charge. It is being installed at the WIPP site in New Mexico, which provides a 2000 meter water-equivalent overburden. EXO-200 will begin taking data in 2009, with themore » expected two-year sensitivity to the half-life for neutrinoless double beta decay of 6.4 x 10{sup 25} years. According to the most recent nuclear matrix element calculations, this corresponds to an effective Majorana neutrino mass of 0.13 to 0.19 eV. It will also measure the two neutrino mode for the first time in {sup 136}Xe.« less

Resolving Past Liabilities for Future Reduction in Greenhouse Gases; Nuclear Energy and the Outstanding Federal Liability of Spent Nuclear Fuel

NASA Astrophysics Data System (ADS)

Donohue, Jay

This thesis will: (1) examine the current state of nuclear power in the U.S.; (2) provide a comparison of nuclear power to both existing alternative/renewable sources of energy as well as fossil fuels; (3) dissect Standard Contracts created pursuant to the National Waste Policy Act (NWPA), Congress' attempt to find a solution for Spent Nuclear Fuel (SNF), and the designation of Yucca Mountain as a repository; (4) the anticipated failure of Yucca Mountain; (5) explore WIPP as well as attempts to build a facility on Native American land in Utah; (6) examine reprocessing as a solution for SNF used by France and Japan; and, finally, (7) propose a solution to reduce GHG's by developing new nuclear energy plants with financial support from the U.S. government and a solution to build a storage facility for SNF through the sitting of a repository based on a "bottom-up" cooperative federalism approach.

RH Packaging Program Guidance

DOE Office of Scientific and Technical Information (OSTI.GOV)

Washington TRU Solutions LLC

The purpose of this program guidance document is to provide the technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package (also known as the "RH-TRU 72-B cask") and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the C of C shall govern. The C of C states: "...each package must be prepared for shipmentmore » and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." It further states: "...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) Contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) §71.8, "Deliberate Misconduct." Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.In accordance with 10 CFR Part 71, "Packaging and Transportation of Radioactive Material," certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21, "Reporting of Defects and Noncompliance," regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations are conducted. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions or equivalent approved instructions. Following these instructions assures that operations meet the requirements of the SARP.« less

RH Packaging Program Guidance

DOE Office of Scientific and Technical Information (OSTI.GOV)

Washington TRU Solutions LLC

The purpose of this program guidance document is to provide the technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the C of C shall govern. The C of C states: "...each package must be prepared for shipment and operated in accordance with the proceduresmore » described in Chapter 7.0, Operating Procedures, of the application." It further states: "...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) Contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 Code of Federal Regulations (CFR) §71.8, "Deliberate Misconduct." Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. In accordance with 10 CFR Part 71, "Packaging and Transportation of Radioactive Material," certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21, "Reporting of Defects and Noncompliance," regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations are conducted. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions or equivalent approved instructions. Following these instructions assures that operations meet the requirements of the SARP.« less

Technical Basis for the Removal of Unremediated Nitrate Salt Sampling (UNS) to Support LANL Treatment Studies

DOE Office of Scientific and Technical Information (OSTI.GOV)

Funk, David John

2016-05-05

The sampling of unremediated nitrate salts (UNS) was originally proposed by the U.S. Department of Energy (DOE) and Los Alamos National Security, LLC (LANS) (collectively, the Permittees) as a means to ensure adequate understanding and characterization of the problematic waste stream created when the Permittees remediated these nitrate salts-bearing waste with an organic absorbent. The proposal to sample the UNS was driven by a lack of understanding with respect to the radioactive contamination release that occurred within the underground repository at the Waste Isolation Pilot Plant (WIPP) in February 14, 2014, as well as recommendations made by a Peer Reviewmore » Team. As discussed, the Permittees believe that current knowledge and understanding of the waste has sufficiently matured such that this additional sampling is not required. Perhaps more importantly, the risk of both chemical and radiological exposure to the workers sampling the UNS drum material is unwarranted. This memo provides the technical justification and rationale for excluding the UNS sampling from the treatment studies.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Bauer, Stephen J.; Urquhart, Alexander

Reconsolidated crushed salt is being considered as a backfilling material placed upon nuclear waste within a salt repository environment. In-depth knowledge of thermal and mechanical properties of the crushed salt as it reconsolidates is critical to thermal/mechanical modeling of the reconsolidation process. An experimental study was completed to quantitatively evaluate the thermal conductivity of reconsolidated crushed salt as a function of porosity and temperature. The crushed salt for this study came from the Waste Isolation Pilot Plant (WIPP). In this work the thermal conductivity of crushed salt with porosity ranging from 1% to 40% was determined from room temperature upmore » to 300°C, using two different experimental methods. Thermal properties (including thermal conductivity, thermal diffusivity and specific heat) of single-crystal salt were determined for the same temperature range. The salt was observed to dewater during heating; weight loss from the dewatering was quantified. The thermal conductivity of reconsolidated crushed salt decreases with increasing porosity; conversely, thermal conductivity increases as the salt consolidates. The thermal conductivity of reconsolidated crushed salt for a given porosity decreases with increasing temperature. A simple mixture theory model is presented to predict and compare to the data developed in this study.« less

IMPLEMENTATION OF DEFENSE NUCLEAR FACILITY SAFETY BOARD RECOMMENDATION 2000-2 AT WIPP

DOE Office of Scientific and Technical Information (OSTI.GOV)

Jackson, K.; Wu, C.

2002-02-26

The Defense Nuclear Safeties Board (DNFSB) issued Recommendation 2000-2 on March 8, 2000, concerning the degrading conditions of vital safety systems, or systems important to nuclear safety, at DOE sites across the nation. The Board recommended that the DOE take action to assess the condition of its nuclear systems to ensure continued operational readiness of vital safety systems that are important for safely accomplishing the DOE's mission. To verify the readiness of vital safety systems, a two-phased approach was established. Phase I consisted of a qualitative assessment to approved criteria of the defined vital safety systems by operating contractor personnel,more » overseen by Federal field office personnel. Based on Phase I Assessment results, vital safety systems with significant deficiencies would be further assessed in Phase II, a more extensive quantitative assessment, by a contractor and Federal team, using a second set of criteria. In addition, Defense Nuclear Facility Safety Board Recommendation 2000-2 concluded that the degradation of confinement ventilation systems was of major concern, and issued a separate set of criteria to perform a Phase II Assessment on confinement ventilation systems.« less

Discussion [of ``The use of conditional simulation in nuclear-waste-site performance assessment`` by Carol A. Gotway

DOE Office of Scientific and Technical Information (OSTI.GOV)

Downing, D.J.

1994-05-01

EPA 40 CFR 191.16 (EPA 1985) states in part that the disposal systems should be designed to provide reasonable expectation that for 1,000 years after disposal, undisturbed performance of the disposal system shall not cause radionuclide concentrations to exceed specified limits. The question is how can one, with the tools that one has today, establish with some degree of confidence that a requirement like that just given will be achieved? Over the last several years, this has been demonstrated through the use of simulation analysis of the system being studied. An example of such a study on nuclear reactor criticalitymore » is described. Then the author discusses Carol Gotway`s study on WIPP. The author believes that work on computer simulation models is extremely important. These are primary tools one has for investigating many complex problems--for example, groundwater contamination, molecular dynamics, climate modeling, and nuclear-reactor accidents. Many of these models are being investigated at the national laboratories but unfortunately often without any help from statisticians. The article by Gotway shows another example of how statistics can be applied to a complicated process to yield practical results.« less

Treatability Variance for Containerised Liquids in Mixed Debris Waste - 12101

DOE Office of Scientific and Technical Information (OSTI.GOV)

Alstatt, Catherine M.

2012-07-01

The TRU Waste Processing Center (TWPC) is a Department of Energy facility whose mission is to receive and process for appropriate disposal legacy Contact Handled (CH) and Remote Handled (RH) waste, including debris waste stored at various DOE Oak Ridge facilities. Acceptable Knowledge (AK) prepared for the waste characterizes the waste as mixed waste, meaning it is both radioactive and regulated under the Resource Conservation and Recovery Act (RCRA). The AK also indicates that a number of the debris waste packages contain small amounts of containerised liquids. The documentation indicates liquid wastes generated in routine lab operations were typically collectedmore » for potential recovery of valuable isotopes. However, during activities associated with decontamination and decommissioning (D and D), some containers with small amounts of liquids were placed into the waste containers with debris waste. Many of these containers now hold from 2.5 milliliters (ml) to 237 ml of liquid; a few contain larger volumes. At least some of these containers were likely empty at the time of generation, but documentation of this condition is lacking. Since WIPP compliant AK is developed on a waste stream basis, rather than an individual container basis, and includes every potential RCRA hazardous constituent within the waste stream, it is insufficient for the purpose of characterizing individual containers of liquid. Debris waste is defined in 40 CFR 268.2(g) as 'solid material exceeding a 60 mm particle size that is intended for disposal and that is: a manufactured object; or plant or animal matter; or natural geologic material'. The definition further states that intact containers of hazardous waste that are not ruptured and that retain at least 75% of their original volume are not debris. The prescribed treatment is removal of intact containers from the debris waste, and treatment of their contents to meet specific Land Disposal Restrictions (LDR) standards. This is true for containers with incidental amounts of liquids, even if the liquid is less than 50% of the total waste volume. Under the proposed variance, all free or containerised liquids (up to 3.8 liters(L)) found in the debris would be treated and returned in solid form to the debris waste stream from which they originated. The waste would then be macro-encapsulated. (author)« less

CH-TRU Waste Content Codes (CH-TRUCON)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Washington TRU Solutions LLC

2007-08-15

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container.more » Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).« less

CH-TRU Waste Content Codes (CH-TRUCON)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Washington TRU Solutions LLC

2007-06-15

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container.more » Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).« less

CH-TRU Waste Content Codes (CH-TRUCON)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Washington TRU Solutions LLC

2007-09-20

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container.more » Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).« less

CH-TRU Waste Content Codes (CH-TRUCON)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Washington TRU Solutions LLC

2006-06-20

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container.more » Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).« less

CH-TRU Waste Content Codes (CH-TRUCON)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Washington TRU Solutions LLC

2006-01-18

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container.more » Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).« less

CH-TRU Waste Content Codes (CH-TRUCON)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Washington TRU Solutions LLC

2006-08-15

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container.more » Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).« less

CH-TRU Waste Content Codes (CH-TRUCON)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Washington TRU Solutions LLC

2006-12-20

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container.more » Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).« less

CH-TRU Waste Content Codes (CH-TRUCON)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Washington TRU Solutions LLC

2007-02-15

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container.more » Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).« less

CH-TRU Waste Content Codes (CH-TRUCON)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Washington TRU Solutions LLC

2006-09-15

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container.more » Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).« less

CH-TRU Waste Content Codes

DOE Office of Scientific and Technical Information (OSTI.GOV)

Washington TRU Solutions LLC

2008-01-16

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container.more » Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).« less

Developing an institutional strategy for transporting defense transuranic waste materials

DOE Office of Scientific and Technical Information (OSTI.GOV)

Guerrero, J.V.; Kresny, H.S.

In late 1988, the US Department of Energy (DOE) expects to begin emplacing transuranic waste materials in the Waste Isolation Pilot Plant (WIPP), an R and D facility to demonstrate the safe disposal of radioactive wastes resulting from defense program activities. Transuranic wastes are production-related materials, e.g., clothes, rags, tools, and similar items. These materials are contaminated with alpha-emitting transuranium radionuclides with half-lives of > 20 yr and concentrations > 100 nCi/g. Much of the institutional groundwork has been done with local communities and the State of New Mexico on the siting and construction of the facility. A key tomore » the success of the emplacement demonstration, however, will be a qualified transportation system together with institutional acceptance of the proposed shipments. The DOE's Defense Transuranic Waste Program, and its contractors, has lead responsibility for achieving this goal. The Joint Integration Office (JIO) of the DOE, located in Albuquerque, New Mexico, is taking the lead in implementing an integrated strategy for assessing nationwide institutional concerns over transportation of defense transuranic wastes and in developing ways to resolve or mitigate these concerns. Parallel prototype programs are under way to introduce both the new packaging systems and the institutional strategy to interested publics and organizations.« less

Hot Cell Liners Category of Transuranic Waste Stored Below Ground within Area G

DOE Office of Scientific and Technical Information (OSTI.GOV)

Jones, Robert Wesley; Hargis, Kenneth Marshall

2014-09-01

A large wildfire called the Las Conchas Fire burned large areas near Los Alamos National Laboratory (LANL) in 2011 and heightened public concern and news media attention over transuranic (TRU) waste stored at LANL’s Technical Area 54 (TA-54) Area G waste management facility. The removal of TRU waste from Area G had been placed at a lower priority in budget decisions for environmental cleanup at LANL because TRU waste removal is not included in the March 2005 Compliance Order on Consent (Reference 1) that is the primary regulatory driver for environmental cleanup at LANL. The Consent Order is an agreementmore » between LANL and the New Mexico Environment Department (NMED) that contains specific requirements and schedules for cleaning up historical contamination at the LANL site. After the Las Conchas Fire, discussions were held by the U.S. Department of Energy (DOE) with the NMED on accelerating TRU waste removal from LANL and disposing it at the Waste Isolation Pilot Plant (WIPP). This report summarizes available information on the origin, configuration, and composition of the waste containers within the Hot Cell Liners category; their physical and radiological characteristics; the results of the radioassays; and the justification to reclassify the five containers as LLW rather than TRU waste.« less

Stable-isotope geochemistry of groundwaters in the Delaware Basin of southeastern New Mexico

DOE Office of Scientific and Technical Information (OSTI.GOV)

Lambert, S.J.; Harvey, D.M.

/sup 18/O//sup 16/O and D/H ratio measurements have been made on groundwaters sampled from the Rustler Formation (Ochoan, Permian) and related rocks in the northern Delaware Basin of southeastern New Mexico. Most confined Rustler waters at the Waste Isolation Pilot Plant (WIPP) site and to the west in Nash Draw and confined waters from the Capitan limestone constitute one population in deltaD/delta/sup 18/O space, while unconfined groundwaters inferred to originate as modern surface recharge to alluvium, sandstones in the Ogallala Formation, the near-surface Rustler in southwestern Nash Draw, and the Capitan vadose zone in the Guadalupe Mountains (Carlsbad Caverns) constitutemore » a distinctly different population; the two do not overlap. A likely explanation for this distinction is that meteoric recharge to most of the Rustler and Capitan took place in the geologic past under climatic conditions significantly different from the present. Available tritium and radiocarbon data are consistent with this hypothesis, and the apparent age of confined groundwaters is in excess of 12,000 radiocarbon years, suggesting that recharge took place under wetter conditions in the late Pleistocene. Processes governing recharge in the Delaware Basin are significantly different from those in the nearby Roswell Artesian Basin, but may be similar to those previously described for the Albuquerque (New Mexico) and Murray (South Australia) Basins. 133 refs.« less

Neptunium(V) and neptunium(VI) solubilities in synthetic brines of interest to the Waste Isolation Pilot Plant (WIPP)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Novak, C.F.; Nitsche, H.; Silber, H.B.

1996-12-31

The solubility of Np(V) and Np(VI) has been measured in three synthetic Na-K-Mg-Cl brines in the presence of CO{sub 2}(g). Experiments were prepared from oversaturation by adding an excess of NpO{sub 2}{sup +} or NpO{sub 2}{sup 2+} to the brines and allowing the neptunium solids to precipitate. Vessels were maintained in contact with fixed CO{sub 2}(g) partial pressures at constant pH and 24 {+-} 1 C. Dissolved Np(V) concentrations decreased several orders of magnitude within the first 100 days of the experiment, while dissolved Np(VI) concentrations decreased initially but then remained relatively constant for more than 400 days. The solidmore » phases formed in all experiments were identified by X-ray powder diffraction as KNpO{sub 2}CO{sub 3}{center_dot}xH{sub 2}O(s). Steady state concentrations for Np(V) are similar to those observed for Pu(V) in the same brines under the same conditions, where Pu occurs predominantly as Pu(V). Similarly, steady state concentrations for Np(VI), which was not reduced over a two year period, compare well with measured Pu(VI) concentrations in the same brines before the Pu(VI) was reduced to Pu(V).« less

New Brunswick Laboratory. Progress report, October 1995--September 1996

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

Fiscal year (FY) 1996 was a very good year for New Brunswick Laboratory (NBL), whose major sponsor is the Office of Safeguards and Security (NN-51) in the US Department of Energy (DOE), Office of Nonproliferation and National Security, Office of Security Affairs. Several projects pertinent to the NBL mission were completed, and NBL`s interactions with partners and customers were encouraging. Among the partners with which NBL interacted in this report period were the International Atomic Energy Agency (IAEA), NN-51. Environmental Program Group of the DOE Chicago Operations Office, International Safeguards Project Office, Waste Isolation Pilot Plant (WIPP), Ukraine Working Group,more » Fissile Materials Assurance Working Group, National Institute of Standards and Technology (NIST), Nuclear Regulatory Commission (NRC), Institute for Reference Materials and Measurements (IRMM) in Belgium, Brazilian/Argentine Agency for Accounting and Control of Nuclear Materials (ABACC), Lockheed Idaho Technologies Company, and other DOE facilities and laboratories. NBL staff publications, participation in safeguards assistance and other nuclear programs, development of new reference materials, involvement in the updating and refinement of DOE documents, service in enhancing the science education of others, and other related activities enhanced NBL`s status among DOE laboratories and facilities. Noteworthy are the facts that NBL`s small inventory of nuclear materials is accurately accounted for, and, as in past years, its materials and human resources were used in peaceful nuclear activities worldwide.« less

Obituary: Charles Latif Hyder, 1930-2004

NASA Astrophysics Data System (ADS)

White, Oran Richard

2004-12-01

My friend and colleague, Charles Hyder, was a true physicist with a sound intuitive grasp of fundamentals in modern physics and the underlying mathematics. I admired his knowledge of the history of modern physics and quantum mechanics when we discussed contemporary problems in interpreting solar observations. He had the ability to present his ideas clearly and persuasively to both students and his colleagues. His insatiable curiosity about life in general led him to consider the effects of nuclear weapons development on the human race. Appreciation of the biological effects of radioactive materials produced in the course of weapons and power reactor development led him to a more public career beyond traditional research. Charles Hyder was born April 18, 1930 in Albuquerque, New Mexico. He graduated from Albuquerque High School and served in the Air Force during the Korean War. He received a BS and MS in physics from the University of New Mexico (1958, 1960) and a PhD in astrogeophysics at the University of Colorado (1964). His positions included the Department of Astronomy and Institute of Geophysics at UCLA (1964-65), Sacramento Peak Solar Observatory (1965-1970) and the Goddard Space Flight Center (1970-1977). He also taught at the University of New Mexico (1970-1977) and was active on the Solar Maximum Mission science team (1970-1977, 1980-1984). He was married twice with both marriages ending in divorce. He and his first wife Ann had three children (Paul, Roxanne and Querida) and he and his second wife Laurie had a son Niels. Charles Hyder's professional career in solar physics began in 1961 during his graduate studies at the Department of AstroGeophysics of the University of Colorado and continued until 1983 when he chose to follow his convictions to expose the threat of nuclear proliferation. His early research was in the study of the quantum mechanics of polarized light produced in the presence of magnetic fields. Application of this work to interpretation of solar spectra was a basic theme in fifty-one papers published between 1963 and 1983. Charles' interest in solar prominences and flares led him to study the physics of in-falling plasma in solar active regions and the production of the so-called "two ribbon" flares associated with active region prominences. His final work in solar physics was done on the Solar Maximum Mission (SMM) in collaboration with colleagues at Goddard Space Flight Center and Marshall Space Flight Center. After 1983, Charles' devoted his full energy to exposing the threat of nuclear weapons and reactor by-products in the biosphere. His was a very public crusade with a seven month fast in Lafayette Park, Washington D.C. and a vigorous opposition to the Waste Isolation Pilot Plant (WIPP) at Carlsbad, New Mexico. His analysis emphasized the need to understand convection of "hot" containers of radioactive waste in the WIPP salt bed. He concluded that the containers would eventually emerge at the surface and be a biological threat. His greatest fear was that dispersal of plutonium in small amounts worldwide was inevitably leading to biological mutation and destruction of life as we know it. We all remember his imposing stature and the strength of his arguments in discussions of life, physics, and the dangers of radioactive materials dispersed on the Earth. He led an unconventional life where he truly reveled in learning and earnestly worked to make a difference.

Test-potentiated learning: three independent replications, a disconfirmed hypothesis, and an unexpected boundary condition.

PubMed

Wissman, Kathryn T; Rawson, Katherine A

2018-04-01

Arnold and McDermott [(2013). Test-potentiated learning: Distinguishing between direct and indirect effects of testing. Journal of Experimental Psychology: Learning, Memory, and Cognition, 39, 940-945] isolated the indirect effects of testing and concluded that encoding is enhanced to a greater extent following more versus fewer practice tests, referred to as test-potentiated learning. The current research provided further evidence for test-potentiated learning and evaluated the covert retrieval hypothesis as an alternative explanation for the observed effect. Learners initially studied foreign language word pairs and then completed either one or five practice tests before restudy occurred. Results of greatest interest concern performance on test trials following restudy for items that were not correctly recalled on the test trials that preceded restudy. Results replicate Arnold and McDermott (2013) by demonstrating that more versus fewer tests potentiate learning when trial time is limited. Results also provide strong evidence against the covert retrieval hypothesis concerning why the effect occurs (i.e., it does not reflect differential covert retrieval during pre-restudy trials). In addition, outcomes indicate that the magnitude of the test-potentiated learning effect decreases as trial length increases, revealing an unexpected boundary condition to test-potentiated learning.

Partial Testing Can Potentiate Learning of Tested and Untested Material from Multimedia Lessons

ERIC Educational Resources Information Center

Yue, Carole L.; Soderstrom, Nicholas C.; Bjork, Elizabeth Ligon

2015-01-01

Test-potentiated learning occurs when testing renders a subsequent study period more effective than it would have been without an intervening test. We examined whether testing only a subset of material from a multimedia lesson would potentiate the restudy of both tested and untested material. In Experiments 1a and 1b, participants studied a…

Learning Potential Tests for Ethnic Minorities.

ERIC Educational Resources Information Center

Hamers, J. H. M.; Pennings, A. H.

1995-01-01

This article presents the results of three studies in the learning-potential testing of children from minority groups: (1) Test of Children's Learning Ability; (2) Learning Efficiency Battery; and (3) Learning Potential Test for Ethnic Minorities. It concludes that, although the development of culture-free tests is impossible, it is possible to…

EVOKED POTENTIALS, PHYSIOLOGICAL METHODS WITH HUMAN APPLICATIONS

EPA Science Inventory

A number of tests and test batteries have been developed and implemented for detecting potential neurotoxicity in humans. n some cases test results may suggest specific dysfunction. hile tests in laboratory animals are often used to project the potential for adverse health effect...

Non-Nuclear Testing of Fission Technologies at NASA MSFC

NASA Technical Reports Server (NTRS)

Houts, Robert G.; Pearson, J. Boise; Aschenbrenner, Kenneth C.; Bradley, David E.; Dickens, Ricky E.; Emrich, William J.; Garber, Anne E.; Godfroy, Thomas J.; Harper, Roger T.; Martin, Jim J.;

DOE Office of Scientific and Technical Information (OSTI.GOV)

Wolery, Thomas J.; Tayne, Andrew; Jove-Colon, Carlos F.

Thermodynamic data are essential for understanding and evaluating geochemical processes, as by speciation-solubility calculations, reaction -path modeling, or reactive transport simulation. These data are required to evaluate both equilibrium states and the kinetic approach to such states (via the affinity term in rate laws). The development of thermodynamic databases for these purposes has a long history in geochemistry (e.g., Garrels and Christ, 1965; Helgeson et al., 1969; Helgeson et al., 1978, Johnson et al., 1992; Robie and Hemingway, 1995), paralleled by related and applicable work in the larger scientific community (e.g., Wagman et al., 1982, 1989; Cox et al., 1989;more » Barin and Platzki, 1995; Binneweis and Milke, 1999). The Yucca Mountain Project developed two qualified thermodynamic databases for to model geochemical processes, including ones involving repository components such as spent fuel. The first of the two (BSC, 2007a) was for systems containing dilute aqueous solutions only, the other (BSC, 2007b) for systems involving concentrated aqueous solutions and incorporating a model for such based on Pitzer’s (1991) equations . A 25°C-only database with similarities to the latter was also developed for WIPP (cf. Xiong, 2005). The YMP dilute systems database is widely used in the geochemistry community for a variety of applications involving rock/water interactions. The purpose of the present task is to improve these databases for work on the Used Fuel Disposition Project and maintain some semblance of order that will support qualification in support of the development of future underground high level nuclear waste disposal.« less

RH-TRU Waste Characterization by Acceptable Knowledge at the Idaho National Engineering and Environmental Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

Schulz, C.; Givens, C.; Bhatt, R.

2003-02-24

Idaho National Engineering and Environmental Laboratory (INEEL) is conducting an effort to characterize approximately 620 drums of remote-handled (RH-) transuranic (TRU) waste currently in its inventory that were generated at the Argonne National Laboratory-East (ANL-E) Alpha Gamma Hot Cell Facility (AGHCF) between 1971 and 1995. The waste was generated at the AGHCF during the destructive examination of irradiated and unirradiated fuel pins, targets, and other materials from reactor programs at ANL-West (ANL-W) and other Department of Energy (DOE) reactors. In support of this effort, Shaw Environmental and Infrastructure (formerly IT Corporation) developed an acceptable knowledge (AK) collection and management programmore » based on existing contact-handled (CH)-TRU waste program requirements and proposed RH-TRU waste program requirements in effect in July 2001. Consistent with Attachments B-B6 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit (HWFP) and th e proposed Class 3 permit modification (Attachment R [RH-WAP] of this permit), the draft AK Summary Report prepared under the AK procedure describes the waste generating process and includes determinations in the following areas based on AK: physical form (currently identified at the Waste Matrix Code level); waste stream delineation; applicability of hazardous waste numbers for hazardous waste constituents; and prohibited items. In addition, the procedure requires and the draft summary report contains information supporting determinations in the areas of defense relationship and radiological characterization.« less

Laboratory correlation of soil swell potential : final report.

DOT National Transportation Integrated Search

1979-03-01

The objective of the study was to determine if a correlation exists between the Potential Volume Change Test and the Potential Vertical Rise Test as compared to the Third Cycle Expansion Pressure Test. In order to accomplish this objective, samples o...

The Application of Surface Potential Test on Hand-making Insulation for Generator Stator End-winding

NASA Astrophysics Data System (ADS)

Lu, Zhu-mao; Liu, Qing; Wang, Tian-zheng; Bai, Lu; Li, Yan-peng

2017-05-01

This paper presents the advantage of surface potential test on hand-making insulation for generator stator end-winding insulation detection, compared with DC or AC withstand voltage test, also details the test principle, connection method and test notes. And through the case, surface potential test on hand-making insulation proved effective for insulation quality detection after generator stator end-winding maintenance, and the experimental data is useful and reliable for the electrical equipment operation and maintenance in the power plant.

Free Recall Enhances Subsequent Learning

PubMed Central

Arnold, Kathleen M.; McDermott, Kathleen B.

2013-01-01

Testing, or retrieval practice, has become a central topic in memory research. One potentially important effect of retrieval practice has received little attention, however: Retrieval practice may enhance, or potentiate, subsequent learning. We introduce a paradigm that can measure the indirect, potentiating effect of free recall tests on subsequent learning, and then test a hypothesis for why tests have this potentiating effect. In two experiments, the benefit of a restudy trial was enhanced when prior free recall tests had been taken. Results from a third correlational study suggest that this effect may be mediated by the effect of testing on organization. Not only do encoding conditions impact later retrievability, but also retrieval attempts impact subsequent encoding effectiveness. PMID:23297100

Non-Nuclear Testing of Space Nuclear Systems at NASA MSFC

NASA Technical Reports Server (NTRS)

Houts, Michael G.; Pearson, Boise J.; Aschenbrenner, Kenneth C.; Bradley, David E.; Dickens, Ricky; Emrich, William J.; Garber, Anne; Godfroy, Thomas J.; Harper, Roger T.; Martin, Jim J.;

34 CFR 668.144 - Application for test approval.

Code of Federal Regulations, 2012 CFR

2012-07-01

... identify potential test irregularities and make a determination that test irregularities have occurred; (ii... of how the State will identify potential test irregularities and make a determination that test... 34 Education 3 2012-07-01 2012-07-01 false Application for test approval. 668.144 Section 668.144...

34 CFR 668.144 - Application for test approval.

Code of Federal Regulations, 2011 CFR

2011-07-01

... identify potential test irregularities and make a determination that test irregularities have occurred; (ii... of how the State will identify potential test irregularities and make a determination that test... 34 Education 3 2011-07-01 2011-07-01 false Application for test approval. 668.144 Section 668.144...

34 CFR 668.144 - Application for test approval.

Code of Federal Regulations, 2013 CFR

2013-07-01

... identify potential test irregularities and make a determination that test irregularities have occurred; (ii... of how the State will identify potential test irregularities and make a determination that test... 34 Education 3 2013-07-01 2013-07-01 false Application for test approval. 668.144 Section 668.144...

34 CFR 668.144 - Application for test approval.

Code of Federal Regulations, 2014 CFR

2014-07-01

... identify potential test irregularities and make a determination that test irregularities have occurred; (ii... of how the State will identify potential test irregularities and make a determination that test... 34 Education 3 2014-07-01 2014-07-01 false Application for test approval. 668.144 Section 668.144...

Wave Energy Prize - 1/50th Testing - Sea Potential

DOE Data Explorer

Wesley Scharmen

2015-12-04

This submission of data includes all the 1/50th scale testing data completed on the Wave Energy Prize for the Sea Potential team, and includes: 1/50th test data (raw & processed) 1/50th test data video and pictures 1/50th Test plans and testing documents SSTF_Submission (summarized results)

Complete Host Range Testing on Common Reed with Potential Biological Control Agents and Investigation into Biological Control for Flowering Rush

DTIC Science & Technology

2016-07-01

ER D C/ EL C R- 16 -5 Aquatic Plant Control Research Program Complete Host Range Testing on Common Reed with Potential Biological...client/default. Aquatic Plant Control Research Program ERDC/EL CR-16-5 July 2016 Complete Host Range Testing on Common Reed with Potential...and started with sequential no-choice oviposition tests. So far, no eggs were found on any of the 22 test plants offered. The authors also found the

Evaluation Tests of Select Fuel Additives for Potential Use in U.S. Army Corps of Engineers Diesel Engines

DTIC Science & Technology

2016-07-01

DOER) program, diesel fuel additives were tested to evaluate their potential for reducing diesel fuel consumption and cost. Four fuel additives were...tested to evaluate their potential for reducing diesel fuel consumption and cost: • An ethanol injection system • Envirofuels Diesel Fuel Catalyst...reduction in select operation conditions, only the ethanol injection system consistently showed potential to reduce diesel fuel consumption , which may be

Free-piston Stirling component test power converter test results and potential Stirling applications

NASA Technical Reports Server (NTRS)

Dochat, G. R.

1992-01-01

As the principal contractor to NASA-Lewis Research Center, Mechanical Technology Incorporated is under contract to develop free-piston Stirling power converters in the context of the competitive multiyear Space Stirling Technology Program. The first generation Stirling power converter, the component test power converter (CTPC) initiated cold end testing in 1991, with hot testing scheduled for summer of 1992. This paper reviews the test progress of the CTPC and discusses the potential of Stirling technology for various potential missions at given point designs of 250 watts, 2500 watts, and 25,000 watts.

Potential use of battery packs from NCAP tested vehicles.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Lamb, Joshua; Orendorff, Christopher J.

2013-10-01

Several large electric vehicle batteries available to the National Highway Traffic Safety Administration are candidates for use in future safety testing programs. The batteries, from vehicles subjected to NCAP crashworthiness testing, are considered potentially damaged due to the nature of testing their associated vehicles have been subjected to. Criteria for safe shipping to Sandia is discussed, as well as condition the batteries must be in to perform testing work. Also discussed are potential tests that could be performed under a variety of conditions. The ultimate value of potential testing performed on these cells will rest on the level of accessmore » available to the battery pack, i.e. external access only, access to the on board monitoring system/CAN port or internal electrical access to the battery. Greater access to the battery than external visual and temperature monitoring would likely require input from the battery manufacturer.« less

Module Hipot and ground continuity test results

NASA Technical Reports Server (NTRS)

Griffith, J. S.

1984-01-01

Hipot (high voltage potential) and module frame continuity tests of solar energy conversion modules intended for deployment into large arrays are discussed. The purpose of the tests is to reveal potentially hazardous voltage conditions in installed modules, and leakage currents that may result in loss of power or cause ground fault system problems, i.e., current leakage potential and leakage voltage distribution. The tests show a combined failure rate of 36% (69% when environmental testing is included). These failure rates are believed easily corrected by greater care in fabrication.

77 FR 41406 - Evaluation of In Vitro Tests for Identifying Eye Injury Hazard Potential of Chemicals and...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-07-13

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Evaluation of In Vitro Tests for Identifying Eye Injury...-animal testing strategies proposed for identifying eye injury hazard potential of chemicals and products... Panel and submission of data from substances tested in in vitro tests for identifying eye injury hazard...

The Potential Impact of Not Being Able to Create Parallel Tests on Expected Classification Accuracy

ERIC Educational Resources Information Center

Wyse, Adam E.

2011-01-01

In many practical testing situations, alternate test forms from the same testing program are not strictly parallel to each other and instead the test forms exhibit small psychometric differences. This article investigates the potential practical impact that these small psychometric differences can have on expected classification accuracy. Ten…

Test-Potentiated Learning: Distinguishing Between Direct and Indirect Effects of Tests

PubMed Central

Arnold, Kathleen M.; McDermott, Kathleen B.

2013-01-01

The facilitative effect of retrieval practice, or testing, on the probability of later retrieval has been the focus of much recent empirical research. A lesser-known benefit of retrieval practice is that it may also enhance the ability of a learner to benefit from a subsequent restudy opportunity. This facilitative effect of retrieval practice on subsequent encoding is known as test-potentiated learning. Thus far, however, the literature has not isolated the indirect effect of retrieval practice on subsequent memory (via enhancing the effectiveness of restudy) from the direct effects of retrieval on subsequent memory. The experiment presented here uses conditional probability to disentangle test-potentiated learning from the direct effects of retrieval practice. The results indicate that unsuccessful retrieval attempts enhance the effectiveness of subsequent restudy, demonstrating that tests do potentiate subsequent learning. PMID:22774852

Measuring Learning Potential: An Alternative to the Traditional Intelligence Test. Studies in Learning Potential, Volume 3, Number 39.

ERIC Educational Resources Information Center

Budoff, Milton

Proposed is the assessment of learning potential through a test-train-retest paradigm in addition to the traditional intelligence test with mentally handicapped or disadvantaged children. Discussed is a rationale for the approach which posits that poor and/or nonwhite children do not have equal access to school-preparatory experiences though they…

Exploring the Potential of Direct-To-Consumer Genomic Test Data for Predicting Adverse Drug Events.

PubMed

Zhang, Patrick M; Sarkar, Indra Neil

2018-01-01

Recent technological advancements in genetic testing and the growing accessibility of public genomic data provide researchers with a unique avenue to approach personalized medicine. This feasibility study examined the potential of direct-to-consumer (DTC) genomic tests (focusing on 23andMe) in research and clinical applications. In particular, we combined population genetics information from the Personal Genome Project with adverse event reports from AEOLUS and pharmacogenetic information from PharmGKB. Primarily, associations between drugs based on co-occurring genetic variations and associations between variants and adverse events were used to assess the potential for leveraging single nucleotide polymorphism information from 23andMe. The results of this study suggest potential clinical uses of DTC tests in light of potential drug interactions. Furthermore, the results suggest great potential for analyzing associations at a population level to facilitate knowledge discovery in the realm of predicting adverse drug events.

Beyond Performance Results: Analyzing the Informational and Developmental Potentials of Standardized Mathematics Tests

ERIC Educational Resources Information Center

di Martino, Pietro; Baccaglini-Frank, Anna

2017-01-01

In this article, we discuss the potential of a critical approach to standardized tests and their results. In particular, we explore and discuss this potential not only for the assessment of students' mathematical competence, but also for teachers' professional development. We identify and describe two kinds of potential: the Informational…

Slow test charge response in a dusty plasma with Kappa distributed electrons and ions

NASA Astrophysics Data System (ADS)

Ali, S.; Eliasson, B.

2017-08-01

The electrostatic potential around a slowly moving test charge is studied in a dusty plasma where the ions and electrons follow a powerlaw Kappa distribution in velocity space. A test charge moving with a speed much smaller than the dust thermal speed gives rise to a short-scale Debye-Hückel potential as well as a long-range far-field potential decreasing as inverse cube of the distance to the test charge along the propagation direction. The potentials are significantly modified in the presence of high-energy tails, modeled by lower spectral indices in the ion and electron Kappa distribution functions. Plasma parameters relevant to laboratory dusty plasmas are discussed.

42 CFR 486.344 - Condition: Evaluation and management of potential donors and organ placement and recovery.

Code of Federal Regulations, 2013 CFR

2013-10-01

... potential donor (including point-of-care testing and blood typing) are conducted by a laboratory that is... chapter. (3) Ensure that the potential donor's blood is typed using two separate blood samples. (4) Document potential donor's record with all test results, including blood type, before organ recovery. (d...

42 CFR 486.344 - Condition: Evaluation and management of potential donors and organ placement and recovery.

Code of Federal Regulations, 2012 CFR

2012-10-01

... potential donor (including point-of-care testing and blood typing) are conducted by a laboratory that is... chapter. (3) Ensure that the potential donor's blood is typed using two separate blood samples. (4) Document potential donor's record with all test results, including blood type, before organ recovery. (d...

42 CFR 486.344 - Condition: Evaluation and management of potential donors and organ placement and recovery.

Code of Federal Regulations, 2014 CFR

2014-10-01

... potential donor (including point-of-care testing and blood typing) are conducted by a laboratory that is... chapter. (3) Ensure that the potential donor's blood is typed using two separate blood samples. (4) Document potential donor's record with all test results, including blood type, before organ recovery. (d...

An Environmental Sentinel Biomonitor System for Drinking Water Protection

DTIC Science & Technology

2008-12-01

threat chemicals. Potential interferences include chemicals commonly used for drinking water disinfection (chlorine and chloramine ), byproducts of...range. Of the potential interferences tested, the ECIS test was affected only by the disinfectants chlorine and chloramine ; chlorine is typically...Industrial and Potential Interfering Chemicals Used to Evaluate ESB System Toxicity Sensors TICs Potential Interferences Acrylonitrile Chloramine

Evaluation of long-term gas hydrate production testing locations on the Alaska North Slope

USGS Publications Warehouse

Collett, Timothy S.; Boswell, Ray; Lee, Myung W.; Anderson, Brian J.; Rose, Kelly K.; Lewis, Kristen A.

2012-01-01

The results of short-duration formation tests in northern Alaska and Canada have further documented the energy-resource potential of gas hydrates and have justified the need for long-term gas-hydrate-production testing. Additional data acquisition and long-term production testing could improve the understanding of the response of naturally occurring gas hydrate to depressurization-induced or thermal-, chemical-, or mechanical-stimulated dissociation of gas hydrate into producible gas. The Eileen gashydrate accumulation located in the Greater Prudhoe Bay area in northern Alaska has become a focal point for gas-hydrate geologic and production studies. BP Exploration (Alaska) Incorporated and ConocoPhillips have each established research partnerships with the US Department of Energy to assess the production potential of gas hydrates in northern Alaska. A critical goal of these efforts is to identify the most suitable site for production testing. A total of seven potential locations in the Prudhoe Bay, Kuparuk River, and Milne Point production units were identified and assessed relative to their suitability as a long-term gas-hydrate-production test sites. The test-site-assessment criteria included the analysis of the geologic risk associated with encountering reservoirs for gas-hydrate testing. The site-selection process also dealt with the assessment of the operational/logistical risk associated with each of the potential test sites. From this review, a site in the Prudhoe Bay production unit was determined to be the best location for extended gas-hydrate-production testing. The work presented in this report identifies the key features of the potential test site in the Greater Prudhoe Bay area and provides new information on the nature of gas-hydrate occurrence and the potential impact of production testing on existing infrastructure at the most favorable sites. These data were obtained from well-log analysis, geological correlation and mapping, and numerical simulation.

Evaluation of long-term gas hydrate production testing locations on the Alaska north slope

USGS Publications Warehouse

Collett, T.S.; Boswell, R.; Lee, M.W.; Anderson, B.J.; Rose, K.; Lewis, K.A.

2011-01-01

The results of short duration formation tests in northern Alaska and Canada have further documented the energy resource potential of gas hydrates and justified the need for long-term gas hydrate production testing. Additional data acquisition and long-term production testing could improve the understanding of the response of naturally-occurring gas hydrate to depressurization-induced or thermal-, chemical-, and/or mechanical-stimulated dissociation of gas hydrate into producible gas. The Eileen gas hydrate accumulation located in the Greater Prudhoe Bay area in northern Alaska has become a focal point for gas hydrate geologic and production studies. BP Exploration (Alaska) Incorporated and ConocoPhillips have each established research partnerships with U.S. Department of Energy to assess the production potential of gas hydrates in northern Alaska. A critical goal of these efforts is to identify the most suitable site for production testing. A total of seven potential locations in the Prudhoe Bay, Kuparuk, and Milne Point production units were identified and assessed relative to their suitability as a long-term gas hydrate production test site. The test site assessment criteria included the analysis of the geologic risk associated with encountering reservoirs for gas hydrate testing. The site selection process also dealt with the assessment of the operational/logistical risk associated with each of the potential test sites. From this review, a site in the Prudhoe Bay production unit was determined to be the best location for extended gas hydrate production testing. The work presented in this report identifies the key features of the potential test site in the Greater Prudhoe Bay area, and provides new information on the nature of gas hydrate occurrence and potential impact of production testing on existing infrastructure at the most favorable sites. These data were obtained from well log analysis, geological correlation and mapping, and numerical simulation. Copyright 2011, Offshore Technology Conference.

Evaluation of long-term gas hydrate production testing locations on the Alaska North Slope

USGS Publications Warehouse

Collett, Timothy; Boswell, Ray; Lee, Myung W.; Anderson, Brian J.; Rose, Kelly K.; Lewis, Kristen A.

2011-01-01

The results of short duration formation tests in northern Alaska and Canada have further documented the energy resource potential of gas hydrates and justified the need for long-term gas hydrate production testing. Additional data acquisition and long-term production testing could improve the understanding of the response of naturally-occurring gas hydrate to depressurization-induced or thermal-, chemical-, and/or mechanical-stimulated dissociation of gas hydrate into producible gas. The Eileen gas hydrate accumulation located in the Greater Prudhoe Bay area in northern Alaska has become a focal point for gas hydrate geologic and production studies. BP Exploration (Alaska) Incorporated and ConocoPhillips have each established research partnerships with U.S. Department of Energy to assess the production potential of gas hydrates in northern Alaska. A critical goal of these efforts is to identify the most suitable site for production testing. A total of seven potential locations in the Prudhoe Bay, Kuparuk, and Milne Point production units were identified and assessed relative to their suitability as a long-term gas hydrate production test site. The test site assessment criteria included the analysis of the geologic risk associated with encountering reservoirs for gas hydrate testing. The site selection process also dealt with the assessment of the operational/logistical risk associated with each of the potential test sites. From this review, a site in the Prudhoe Bay production unit was determined to be the best location for extended gas hydrate production testing. The work presented in this report identifies the key features of the potential test site in the Greater Prudhoe Bay area, and provides new information on the nature of gas hydrate occurrence and potential impact of production testing on existing infrastructure at the most favorable sites. These data were obtained from well log analysis, geological correlation and mapping, and numerical simulation.

Clinical pharmacogenomics: patient perspectives of pharmacogenomic testing and the incidence of actionable test results in a chronic disease cohort.

PubMed

Mukherjee, Chandrama; Sweet, Kevin M; Luzum, Jasmine A; Abdel-Rasoul, Mahmoud; Christman, Michael F; Kitzmiller, Joseph P

2017-09-01

This study aimed to examine pharmacogenomic test results and patient perspectives at an academic cardiovascular medicine clinic. Test results for three common cardiovascular drug-gene tests (warfarin- CYP2C9-VKORC1 , clopidogrel- CYP2C19 and simvastatin- SLCO1B1 ) of 208 patients in the Ohio State University-Coriell Personalized Medicine Collaborative were examined to determine the incidence of potentially actionable test results. A post-hoc, anonymous, patient survey was also conducted. Potentially actionable test results for at least one of the three drug-gene tests were determined in 170 (82%) patients. Survey responses (n = 134) suggested that patients generally considered their test results to be important (median of 7.5 on a 10-point scale of importance) and were interested (median of 7.3 on a 10-point scale of interest) in a Clinical Pharmacogenomic Service. Attitudes toward pharmacogenomic testing were generally favorable, and potentially actionable test results were not uncommon in this cardiovascular medicine cohort.

Satellite Power Systems (SPS). LSST systems and integration task for SPS flight test article

NASA Technical Reports Server (NTRS)

Greenberg, H. S.

1981-01-01

This research activity emphasizes the systems definition and resulting structural requirements for the primary structure of two potential SPS large space structure test articles. These test articles represent potential steps in the SPS research and technology development.

BioMig--A Method to Evaluate the Potential Release of Compounds from and the Formation of Biofilms on Polymeric Materials in Contact with Drinking Water.

PubMed

Wen, Gang; Kötzsch, Stefan; Vital, Marius; Egli, Thomas; Ma, Jun

2015-10-06

In contact with water, polymeric materials (plastics) release compounds that can support suspended microbial growth and/or biofilm formation. The different methods presently used in the European Union to test plastics take 7-16 weeks to obtain a result. In industry, this delays material and product development as well as quality testing. Therefore, we developed a method package (BioMig) that allows testing of plastic materials with high reproducibility in 2 weeks for their potential biofilm (or biomass) formation and release of carbonaceous migration products when in contact with water. BioMig consists of (i) an extended migration potential test (seven times for 24 h at 60 °C), based on the European norm EN 12873-1 and the German UBA (Umweltbundesamt) guideline, and (ii) a biomass formation potential (BFP) test (14 days at 30 °C), which is a modified version of the Dutch biofilm production potential test. In the migration potential test, the amount of carbon released into water by the specimen is quantified by monitoring total and assimilable organic carbon over time; furthermore, the modular design of the test also allows one to assess additional parameters such as pathogen growth potential on the migration water or toxic effects on microbial growth. Flow cytometry (FCM)-based total cell counting (TCC) is used to quantify microbial growth in suspension and on surfaces after removal with mild sonication without affecting cell integrity. The BFP test allows one to determine both the planktonic (pBFP) and the sessile (sBFP) cell fractions. The sBFP consists of surface-attached cells after removal (>90% efficiency). Results for four standard test materials (PE-Xa, PE-Xc, EPDM 2%, and EPDM 20%), plus positive (PVC-P) and negative (glass) controls are presented. FCM-based TCC demonstrates that the release of growth-supporting carbon and proliferation of surface-attached cells stops increasing and stabilizes after 14 days of incubation; this allows for faster assessment of growth-supporting properties of plastics with BioMig compared to established tests.

Anticipating the potential for positive uptake and adaptation in the implementation of a publicly funded online STBBI testing service: a qualitative analysis.

PubMed

Chabot, Cathy; Gilbert, Mark; Haag, Devon; Ogilvie, Gina; Hawe, Penelope; Bungay, Vicky; Shoveller, Jean A

2018-01-30

Online health services are a rapidly growing aspect of public health provision, including testing for sexually transmitted and other blood-borne infections (STBBI). Generally, healthcare providers, policymakers, and clients imbue online approaches with great positive potential (e.g., encouraging clients' agency; providing cost-effective services to more clients). However, the promise of online health services may vary across contexts and be perceived in negative or ambiguous ways (e.g., risks to 'gold standard' care provision; loss of provider control over an intervention; uncertainty related to budget implications). This study examines attitudes and perceptions regarding the development of a novel online STBBI testing service in Vancouver, Canada. We examine the perceptions about the intervention's potential by interviewing practitioners and planners who were engaged in the development and initial implementation of this testing service. We conducted in-depth interviews with 37 healthcare providers, administrators, policymakers, and community-based service providers engaged in the design and launch of the new online STBBI testing service. We also conducted observations during planning and implementation meetings for the new service. Thematic analysis techniques were employed to identify codes and broader discursive themes across the interview transcripts and observation notes. Some study participants expressed concern that the potential popularity of the new testing service might increase demand on existing sexual health services or become fiscally unsustainable. However, most participants regarded the new service as having the potential to improve STBBI testing in several ways, including reducing waiting times, enhancing privacy and confidentiality, appealing to more tech-savvy sub-populations, optimizing the redistribution of demands on face-to-face service provision, and providing patient-centred technology to empower clients to seek testing. Participants perceived this online STBBI testing service to have the potential to improve sexual health care provision. But, they also anticipated actions-and-reactions, revealing a need to monitor ongoing implementation dynamics. They also identified the larger, potentially system-transforming dimension of the new technology, which enables new system drivers (consumers) and reduces the amount of control health care providers have over online STBBI testing compared to conventional in-person testing.

[Measurement of nasal transepithelial potential difference: a diagnostic test for cystic fibrosis].

PubMed

Charfi, M R; Matran, R; Regnard, J; Lockhart, A

1996-01-01

Measurement of nasal transepithelial potential difference allows the exploration of transepithelial ionic transports in vivo. Cystic fibrosis is an interesting indication of this test. Indeed, this disease is characterized by a chloride and water secretion deficit across respiratory epithelium. We have measured nasal potential in 8 healthy volunteers. Measurements were repeated 3 times a day, during 3 days for each subject. The reproducibility of the data was analysed with factorial variance model. The mean nasal potential in the healthy volunteers group and in 10 patients with cystic fibrosis was compared. In the cystic fibrosis group, the nasal potential was measured 3 times with a 2 mn-interval between the measurements. No significant variation of the nasal potential values was found from day to day or in the same day from one measurement to another. Mean value was -19 +/- 3.5 mv in normal subjects and -42.6 +/- 5.1 mv in cystic fibrosis patients. We conclude that nasal potential measurement is an easy and reproducible test that might be a complementary tool routinely used along with the classical tests in the diagnosis of cystic fibrosis.

Prediction of the developmental toxicity hazard potential of halogenated drinking water disinfection by-products tested by the in vitro hydra assay

DOE Office of Scientific and Technical Information (OSTI.GOV)

Fu, L.J.; Johnson, E.M.; Newman, L.M.

A series of seven randomly selected potential halogenated water disinfection by-products were evaluated in vitro by the hydra assay to determine their developmental toxicity hazard potential. For six of the chemicals tested by this assay (dibromoacetonitrile; trichloroacetonitrile; 2-chlorophenol; 2,4,6-trichlorophenol; trichloroacetic acid; dichloroacetone) it was predicted that they would be generally equally toxic to both adult and embryonic mammals when studied by means of standard developmental toxicity teratology tests. However, the potential water disinfection by-product chloroacetic acid (CA) was determined to be over eight times more toxic to the embryonic developmental portion of the assay than it was to the adults.more » Because of this potential selectivity, CA is a high-priority item for developmental toxicity tests in pregnant mammals to confirm or refute its apparent unique developmental hazard potential and/or to establish a NOAEL by the route of most likely human exposure.« less

The Use of Test Accommodations as a Gaming Strategy: A State-Level Exploration of Potential Gaming Tendencies in the 2007-2009 Period and Implications for Re-Directing Research on Gaming through Test Accommodations

ERIC Educational Resources Information Center

Saatcioglu, Argun; Skrtic, Thomas M.; DeLuca, Thomas A.

2016-01-01

The overuse of test accommodations (e.g., test readers, extra time, and calculators) for students with disabilities is a potential means of gaming the accountability system because it can inflate proficiency gains. However, no direct evidence on this problem exists, and findings on whether or not test accommodations improve test scores are…

Correlations among assays of porcine semen quality following cryopreservation.

PubMed

Hammitt, D G; Martin, P A

1989-09-01

Correlations between in vitro tests of semen quality, used to predict the in vivo fertilizing potential of sperm, indicate that the tests may substitute for each other in predicting fertilizing potential. Lack of correlation between tests suggest that both tests should be used to estimate the fertilizing potential. The purpose of this study was to establish correlations between several in vitro tests of porcine semen quality following freezing. Tests of motility with and without caffeine, spermatozoa with normal apical ridges, sephadex filtration with and without caffeine and acrosin activity were all correlated with each other. Correlations among these tests ranged from 0.45 to 0.83 (P<0.05). Assays for glutamic oxalacetic transaninase (GOT) were not consistently correlated with other tests. None of these tests of semen quality were correlated with the sperm penetration assay except for the test of motility without caffeine, which was correlated with the number of penetrations per hamster oocyte (r = 0.71, P<0.05).

Effects of Muscle Atrophy on Motor Control: Cage-size Effects

NASA Technical Reports Server (NTRS)

Stuart, D. G.

1985-01-01

Two populations of male Sprague-Dawley rats were raised either in conventional minimum-specification cages or in a larger cage. When the animals were mature (125 to 150 d), the physiological status of the soleus (SOL) and extensor digitorum longus (EDL) muscles of the small- and large-cage animals were compared. Analysis of whole-muscle properties including the performance of the test muscle during a standardized fatigue test in which the nerve to the test muscle was subjected to supramaximal intermittent stimulation shows: (1) the amplitude, area, mean amplitude, and peak-to-peak rate of the compound muscle action potential decreased per the course of the fatigue test; (2) cage size did not affect the profile of changes for any of the action-potential measurements; (3) changes exhibited in the compound muscle action potential by SOL and EDL were substantially different; and (4) except for SOL of the large-cage rats, there was a high correlation between all four measures of the compound muscle action potential and the peak tetanic force during the fatigue test; i.e., either the electrical activity largely etermines the force profile during the fatigue test or else contractile-related activity substantially affects the compound muscle action potential.

Measuring learning potential in people with schizophrenia: A comparison of two tasks.

PubMed

Rempfer, Melisa V; McDowd, Joan M; Brown, Catana E

2017-12-01

Learning potential measures utilize dynamic assessment methods to capture performance changes following training on a cognitive task. Learning potential has been explored in schizophrenia research as a predictor of functional outcome and there have been calls for psychometric development in this area. Because the majority of learning potential studies have utilized the Wisconsin Card Sorting Test (WCST), we extended this work using a novel measure, the Rey Osterrieth Complex Figure Test (ROCFT). This study had the following aims: 1) to examine relationships among different learning potential indices for two dynamic assessment tasks, 2) to examine the association between WCST and ROCFT learning potential measures, and 3) to address concurrent validity with a performance-based measure of functioning (Test of Grocery Shopping Skills; TOGSS). Eighty-one adults with schizophrenia or schizoaffective disorder completed WCST and ROCFT learning measures and the TOGSS. Results indicated the various learning potential computational indices are intercorrelated and, similar to other studies, we found support for regression residuals and post-test scores as optimal indices. Further, we found modest relationships between the two learning potential measures and the TOGSS. These findings suggest learning potential includes both general and task-specific constructs but future research is needed to further explore this question. Copyright © 2017 Elsevier B.V. All rights reserved.

Investigating CSI: portrayals of DNA testing on a forensic crime show and their potential effects.

PubMed

Ley, Barbara L; Jankowski, Natalie; Brewer, Paul R

2012-01-01

The popularity of forensic crime shows such as CSI has fueled debate about their potential social impact. This study considers CSI's potential effects on public understandings regarding DNA testing in the context of judicial processes, the policy debates surrounding crime laboratory procedures, and the forensic science profession, as well as an effect not discussed in previous accounts: namely, the show's potential impact on public understandings of DNA and genetics more generally. To develop a theoretical foundation for research on the "CSI effect," it draws on cultivation theory, social cognitive theory, and audience reception studies. It then uses content analysis and textual analysis to illuminate how the show depicts DNA testing. The results demonstrate that CSI tends to depict DNA testing as routine, swift, useful, and reliable and that it echoes broader discourses about genetics. At times, however, the show suggests more complex ways of thinking about DNA testing and genetics.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Goldston, W.

On April 21, 2009, the Energy Facilities Contractors Group (EFCOG) Waste Management Working Group (WMWG) provided a recommendation to the Department of Energy's Environmental Management program (DOE-EM) concerning supplemental guidance on blending methodologies to use to classify waste forms to determine if the waste form meets the definition of Transuranic (TRU) Waste or can be classified as Low-Level Waste (LLW). The guidance provides specific examples and methods to allow DOE and its Contractors to properly classify waste forms while reducing the generation of TRU wastes. TRU wastes are much more expensive to characterize at the generator's facilities, ship, and thenmore » dispose at the Waste Isolation Pilot Plant (WIPP) than Low-Level Radioactive Waste's disposal. Also the reduction of handling and packaging of LLW is inherently less hazardous to the nuclear workforce. Therefore, it is important to perform the characterization properly, but in a manner that minimizes the generation of TRU wastes if at all possible. In fact, the generation of additional volumes of radioactive wastes under the ARRA programs, this recommendation should improve the cost effective implementation of DOE requirements while properly protecting human health and the environment. This paper will describe how the message of appropriate, less expensive, less hazardous blending of radioactive waste is the 'right' thing to do in many cases, but can be confused with inappropriate 'dilution' that is frowned upon by regulators and stakeholders in the public. A proposal will be made in this paper on how to communicate this very complex and confusing technical issue to regulatory bodies and interested stakeholders to gain understanding and approval of the concept. The results of application of the proposed communication method and attempt to change the regulatory requirements in this area will be discussed including efforts by DOE and the NRC on this very complex subject.« less

33 Shafts Category of Transuranic Waste Stored Below Ground within Area G

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hargis, Kenneth Marshall; Monk, Thomas H

This report compiles information to support the evaluation of alternatives and analysis of regulatory paths forward for the 33 shafts. The historical information includes a form completed by waste generators for each waste package (Reference 6) that included a waste description, estimates of Pu-239 and uranium-235 (U-235) based on an accounting technique, and calculations of mixed fission products (MFP) based on radiation measurements. A 1979 letter and questionnaire (Reference 7) provides information on waste packaging of hot cell waste and the configuration of disposal shafts as storage in the 33 Shafts was initiated. Tables of data by waste package weremore » developed during a review of historical documents that was performed in 2005 (Reference 8). Radiological data was coupled with material-type data to estimate the initial isotopic content of each waste package and an Oak Ridge National Laboratory computer code was used to calculate 2009 decay levels. Other sources of information include a waste disposal logbook for the 33 shafts (Reference 9), reports that summarize remote-handled waste generated at the CMR facility (Reference 10) and placement of waste in the 33 shafts (Reference 11), a report on decommissioning of the LAMPRE reactor (Reference 12), interviews with an employee and manager involved in placing waste in the 33 shafts (References 13 and 14), an interview with a long-time LANL employee involved in waste operations (Reference 15), a 2002 plan for disposition of remote-handled TRU waste (Reference 16), and photographs obtained during field surveys of several shafts in 2007. The WIPP Central Characterization Project (CCP) completed an Acceptable Knowledge (AK) summary report for 16 canisters of remote-handled waste from the CMR Facility that contains information relevant to the 33 Shafts on hot-cell operations and timeline (Reference 17).« less

Geologic and well-construction data for the H-8 borehole complex near the proposed Waste Isolation Pilot Plant site, southeastern New Mexico

USGS Publications Warehouse

Wells, J.G.; Drellack, S.L.

1982-01-01

The H-8 complex, a group of three closely-spaced boreholes, is located 9 miles south of the proposed Waste Isolation Pilot Plant site in southeastern Eddy County, New Mexico. The holes were drilled during July, August, and September of 1979 to obtain geologic and hydrologic data to better define the regional ground-water-flow system. The geologic data presented in this report are part of a site-characterization study for the possible disposal of defense-associated radioactive wastes within salt beds of the Salado Formation of Permian age. The geologic data include detailed descriptions of cores, cuttings, and geophysical logs. Each borehole was designed to penetrate a distinct water-bearing zone: H-8a (total depth 505 feet) was completed just below the Magenta Dolomite Member of the Rustler Formation of Permian Age; H-8b (total depth 624 feet) was completed just belows the Culebra Dolomite Member of the Rustler Formation; and H-8c (total depth 808 feet) was completed just below the Rustler Formation-Salado Formation contact. The geologic units penetrated in borehole H-8c are surficial alluvium and eolian sand of Holocene age (0-4 feet); the Mescalero caliche (4-10 feet) and Gatuna Formation (10-153 feet) , both of Pleistocene age; and the Dewey Lake Red Beds (153-399 feet), the Rustler Formation (399-733 feet), and part of the Salado Formation penetrated by borehole H-8c is composed of residue from dissolution of halite and associated rocks, and the hydration of anhydrite to gypsum, indicating that the eastward-moving dissolution front on top of the Salado, found just to the west of the WIPP site, has reached the H-8 site. (USGS)

Geologic and well-construction data for the H-10 borehole complex near the proposed Waste Isolation Pilot Plant site, southeastern New Mexico

USGS Publications Warehouse

Wells, J.G.; Drellack, S.L.

1983-01-01

The H-10 borehole complex, a group of three closely spaced boreholes, is located 3 1/2 miles southeast of the proposed Waste Isolation Pilot Plant site in west-central Lea County, New Mexico. The geological data presented in this report are part of a site-characterization study for the possible storage of defense-associated radioactive wastes within salt beds of the Salado Formation of Permian age. Each borehole was designated to penetrate a distinct water-bearing zone: H-10a (total depth 1 ,318 feet) was completed just below the Magenta Dolomite Member of the Rustler Formation of Permian age; H-10b (total depth 1 ,398 feet) was completed just below the Culebra Dolomite Member of the Rustler Formation; and H-10c (total depth 1,538 feet) was completed below the Rustler Formation-Salado Formation contact. The geologic units penetrated in borehole H-10c are surficial alluvium and eolian sand of Holocene age (0-5 feet); the Mescalero caliche (5-9 feet) and the Gatuna Formation (9-90 feet) of Pleistocene age; formation in the Dockum Group (Chinle Formation, 90-482 feet and Santa Rosa Sandstone, 482-658 feet) of Late Triassic age; and the Dewey Lake Red Beds (658-1,204 feet), the Rustler Formation (1,204-1,501 feet), and part of the Salado Formation (1,501-1,538 feet), all of Permian age. The sections of the Rustler and Salado Formations penetrated by borehole H-10c are complete and contain little or no evidence of dissolution of halite and associated rocks, indicating that the eastward-moving dissolution on top of the Salado, found just to the west of the WIPP site, has not reached the H-10 site. (USGS)

Ovarian Low Malignant Potential Tumors Symptoms, Tests, Prognosis, and Stages (PDQ®)—Patient Version

Cancer.gov

Ovarian low malignant potential tumor (OLMPT) forms in the tissue covering the ovary. OLMPT are made up of abnormal cells that may become cancer, but usually do not. Learn about signs and symptoms, tests to diagnose, and stages of ovarian low malignant potential tumors.

Impact of single particle oscillations on screening of a test charge

NASA Astrophysics Data System (ADS)

Ramazanov, Tlekkabul S.; Moldabekov, Zhandos A.; Gabdullin, Maratbek T.

2018-06-01

Screening of a test charge by electrons oscillating in an external alternating electrical (laser) field is analyzed. It is shown that single particle oscillations lead to the creation of an oscillatory pattern of the test charge's potential at large distances. Analysis has been done by considering and neglecting the contribution of ions on the screening. Impact of the quantum diffraction (non-locality) and of the collisional damping on the test charge's potential is considered. It is shown that electrons are unable to provide screening of the test charge if the frequency of the induced single particle oscillations larger than the electron-plasma frequency. In the opposite case of low frequencies, the potential of the test charge changes its sign if the screening by ions is neglected.

Parameter estimation uncertainty: Comparing apples and apples?

NASA Astrophysics Data System (ADS)

Hart, D.; Yoon, H.; McKenna, S. A.

2012-12-01

Given a highly parameterized ground water model in which the conceptual model of the heterogeneity is stochastic, an ensemble of inverse calibrations from multiple starting points (MSP) provides an ensemble of calibrated parameters and follow-on transport predictions. However, the multiple calibrations are computationally expensive. Parameter estimation uncertainty can also be modeled by decomposing the parameterization into a solution space and a null space. From a single calibration (single starting point) a single set of parameters defining the solution space can be extracted. The solution space is held constant while Monte Carlo sampling of the parameter set covering the null space creates an ensemble of the null space parameter set. A recently developed null-space Monte Carlo (NSMC) method combines the calibration solution space parameters with the ensemble of null space parameters, creating sets of calibration-constrained parameters for input to the follow-on transport predictions. Here, we examine the consistency between probabilistic ensembles of parameter estimates and predictions using the MSP calibration and the NSMC approaches. A highly parameterized model of the Culebra dolomite previously developed for the WIPP project in New Mexico is used as the test case. A total of 100 estimated fields are retained from the MSP approach and the ensemble of results defining the model fit to the data, the reproduction of the variogram model and prediction of an advective travel time are compared to the same results obtained using NSMC. We demonstrate that the NSMC fields based on a single calibration model can be significantly constrained by the calibrated solution space and the resulting distribution of advective travel times is biased toward the travel time from the single calibrated field. To overcome this, newly proposed strategies to employ a multiple calibration-constrained NSMC approach (M-NSMC) are evaluated. Comparison of the M-NSMC and MSP methods suggests that M-NSMC can provide a computationally efficient and practical solution for predictive uncertainty analysis in highly nonlinear and complex subsurface flow and transport models. This material is based upon work supported as part of the Center for Frontiers of Subsurface Energy Security, an Energy Frontier Research Center funded by the U.S. Department of Energy, Office of Science, Office of Basic Energy Sciences under Award Number DE-SC0001114. Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000.

Joint inversion of hydraulic head and self-potential data associated with harmonic pumping tests

NASA Astrophysics Data System (ADS)

Soueid Ahmed, A.; Jardani, A.; Revil, A.; Dupont, J. P.

2016-09-01

Harmonic pumping tests consist in stimulating an aquifer by the means of hydraulic stimulations at some discrete frequencies. The inverse problem consisting in retrieving the hydraulic properties is inherently ill posed and is usually underdetermined when considering the number of well head data available in field conditions. To better constrain this inverse problem, we add self-potential data recorded at the ground surface to the head data. The self-potential method is a passive geophysical method. Its signals are generated by the groundwater flow through an electrokinetic coupling. We showed using a 3-D saturated unconfined synthetic aquifer that the self-potential method significantly improves the results of the harmonic hydraulic tomography. The hydroelectric forward problem is obtained by solving first the Richards equation, describing the groundwater flow, and then using the result in an electrical Poisson equation describing the self-potential problem. The joint inversion problem is solved using a reduction model based on the principal component geostatistical approach. In this method, the large prior covariance matrix is truncated and replaced by its low-rank approximation, allowing thus for notable computational time and storage savings. Three test cases are studied, to assess the validity of our approach. In the first test, we show that when the number of harmonic stimulations is low, combining the harmonic hydraulic and self-potential data does not improve the inversion results. In the second test where enough harmonic stimulations are performed, a significant improvement of the hydraulic parameters is observed. In the last synthetic test, we show that the electrical conductivity field required to invert the self-potential data can be determined with enough accuracy using an electrical resistivity tomography survey using the same electrodes configuration as used for the self-potential investigation.

78 FR 49287 - Environmental Assessment for Potential Lease Issuance and Marine Hydrokinetic Technology Testing...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-08-13

...; MMAA104000] Environmental Assessment for Potential Lease Issuance and Marine Hydrokinetic Technology Testing... important environmental issues associated with data collection and technology testing activities (76 FR... Availability of a Revised Environmental Assessment and a Finding of No Significant Impact. SUMMARY: BOEM has...

Potential generated inner and outside a circular wire in its plane. Application to Saturn's ring

NASA Astrophysics Data System (ADS)

Najid, N.-E.; Zegoumou, M.; El Ourabi, E. H.

2012-12-01

In this article we derive the development of the potential generated by a homogeneous wire bent into a circular shape (Najid, Jammari & Zegoumou, 2005). We develop the potential as a power series of the distance from an appropriate origin to the test particle. The potential is expressed as a function of Legendre polynomials. We study both, the case where the test particle is inside or outside the circular wire. By Lagrangian formulation, we establish the differential equation of motion. The numerical resolution leads us to different orbits. Outside the wire we get a case where the test particle is confined between a maxima and minima of the radial position; while inner the wire the test particle is subjected to an escape case depending on the time of integration.

The Impact on DoD of the Toxic Substances Control Act

DTIC Science & Technology

1980-06-01

reconcile a limit of 10 ppm in the gasoline area where there is a potential for 400,000 exposures while in the rubber industry the potential is only 150,000...that the Ames test and other mutagenic tests are predictive of tumor producing potential. Many of us in toxi - cology are not impressed with this...also be completely different; so much for generic toxi - cology and for the possibility that short term testing for mutagenic effects is predictive of

Complete Host Testing with a Potential Biological Control Agent on Common Reed in View of Submitting a Petition for Field Release in Winter 2014/15

DTIC Science & Technology

2014-12-01

natural field setting. Leaf sheaths of native reed are looser and tend to fall off before winter. Ovipositing females might notice the difference and...Interim Report August-December 2014 Contract No. W911NF-14-1-0510 Project title: Complete host testing with a potential ...4. TITLE AND SUBTITLE Complete host testing with a potential biological control agent on common reed in view of submitting a petition for field

Direct-to-consumer online genetic testing and the four principles: an analysis of the ethical issues.

PubMed

Wasson, Katherine; Cook, E David; Helzlsouer, Kathy

2006-01-01

The development of genetic tests marketed and sold direct-to-consumers (DTC) via the internet raises moral concerns and debate about their appropriateness and ethical and clinical significance. These tests are offered for a wide range of diseases and conditions, and the mutations have variable penetrance and associated risk. A number of these tests lack data on their accuracy and reliability, making interpretation of results difficult. DTC genetic testing is undertaken outside the context of the physician-patient relationship and may lack appropriate individual and family genetic counseling, leaving the consumer vulnerable to potential harms, such as misinterpretation of results, including false positive or false reassurance, with limited or no benefits. Beauchamp and Childress's four principles of biomedical ethics provide a framework for analyzing the ethical issues raised by DTC genetic testing. We argue that the potential harms outweigh the potential benefits of such tests, that respect for autonomy should be limited in light of potential harm from DTC testing, and that the availability of genetic testing over the internet may be considered unfair and unjust and affect resource allocation by placing an unfair burden on primary care physicians. In light of the moral issues posed by these tests, practical responses are suggested in the areas of consumer education, medical education, and interaction with commercial companies.

Cytogenotoxicity screening of source water, wastewater and treated water of drinking water treatment plants using two in vivo test systems: Allium cepa root based and Nile tilapia erythrocyte based tests.

PubMed

Hemachandra, Chamini K; Pathiratne, Asoka

2017-01-01

Biological effect directed in vivo tests with model organisms are useful in assessing potential health risks associated with chemical contaminations in surface waters. This study examined the applicability of two in vivo test systems viz. plant, Allium cepa root based tests and fish, Oreochromis niloticus erythrocyte based tests for screening cytogenotoxic potential of raw source water, water treatment waste (effluents) and treated water of drinking water treatment plants (DWTPs) using two DWTPs associated with a major river in Sri Lanka. Measured physico-chemical parameters of the raw water, effluents and treated water samples complied with the respective Sri Lankan standards. In the in vivo tests, raw water induced statistically significant root growth retardation, mitodepression and chromosomal abnormalities in the root meristem of the plant and micronuclei/nuclear buds evolution and genetic damage (as reflected by comet scores) in the erythrocytes of the fish compared to the aged tap water controls signifying greater genotoxicity of the source water especially in the dry period. The effluents provoked relatively high cytogenotoxic effects on both test systems but the toxicity in most cases was considerably reduced to the raw water level with the effluent dilution (1:8). In vivo tests indicated reduction of cytogenotoxic potential in the tested drinking water samples. The results support the potential applications of practically feasible in vivo biological test systems such as A. cepa root based tests and the fish erythrocyte based tests as complementary tools for screening cytogenotoxicity potential of the source water and water treatment waste reaching downstream of aquatic ecosystems and for evaluating cytogenotoxicity eliminating efficacy of the DWTPs in different seasons in view of human and ecological safety. Copyright © 2016 Elsevier Ltd. All rights reserved.

Ground correlation investigation of thruster spacecraft interactions to be measured on the IAPS flight test

NASA Technical Reports Server (NTRS)

Power, J. L.

1984-01-01

Preliminary ground correlation testing has been conducted with an 8 cm mercury ion thruster and diagnostic instrumentation replicating to a large extent the IAPS flight test hardware, configuration, and electrical grounding/isolation. Thruster efflux deposition retained at 25 C was measured and characterized. Thruster ion efflux was characterized with retarding potential analyzers. Thruster-generated plasma currents, the spacecraft common (SCC) potential, and ambient plasma properties were evaluated with a spacecraft potential probe (SPP). All the measured thruster/spacecraft interactions or their IAPS measurements depend critically on the SCC potential, which can be controlled by a neutralizer ground switch and by the SPP operation.

Promoted Combustion Test Propagation Rate Data

NASA Technical Reports Server (NTRS)

Borstorff, J.; Jones, P.; Lowery, F.

2002-01-01

Combustion propagation rate data were examined for potential use in benchmarking a thermal model of the Promoted Combustion Test (PCT), and also for potential use in measuring the repeatability of PCT results.

Reconstruction of the water table from self-potential data: a bayesian approach.

PubMed

Jardani, A; Revil, A; Barrash, W; Crespy, A; Rizzo, E; Straface, S; Cardiff, M; Malama, B; Miller, C; Johnson, T

2009-01-01

Ground water flow associated with pumping and injection tests generates self-potential signals that can be measured at the ground surface and used to estimate the pattern of ground water flow at depth. We propose an inversion of the self-potential signals that accounts for the heterogeneous nature of the aquifer and a relationship between the electrical resistivity and the streaming current coupling coefficient. We recast the inversion of the self-potential data into a Bayesian framework. Synthetic tests are performed showing the advantage in using self-potential signals in addition to in situ measurements of the potentiometric levels to reconstruct the shape of the water table. This methodology is applied to a new data set from a series of coordinated hydraulic tomography, self-potential, and electrical resistivity tomography experiments performed at the Boise Hydrogeophysical Research Site, Idaho. In particular, we examine one of the dipole hydraulic tests and its reciprocal to show the sensitivity of the self-potential signals to variations of the potentiometric levels under steady-state conditions. However, because of the high pumping rate, the response was also influenced by the Reynolds number, especially near the pumping well for a given test. Ground water flow in the inertial laminar flow regime is responsible for nonlinearity that is not yet accounted for in self-potential tomography. Numerical modeling addresses the sensitivity of the self-potential response to this problem.

Potential for false positive HIV test results with the serial rapid HIV testing algorithm.

PubMed

Baveewo, Steven; Kamya, Moses R; Mayanja-Kizza, Harriet; Fatch, Robin; Bangsberg, David R; Coates, Thomas; Hahn, Judith A; Wanyenze, Rhoda K

2012-03-19

Rapid HIV tests provide same-day results and are widely used in HIV testing programs in areas with limited personnel and laboratory infrastructure. The Uganda Ministry of Health currently recommends the serial rapid testing algorithm with Determine, STAT-PAK, and Uni-Gold for diagnosis of HIV infection. Using this algorithm, individuals who test positive on Determine, negative to STAT-PAK and positive to Uni-Gold are reported as HIV positive. We conducted further testing on this subgroup of samples using qualitative DNA PCR to assess the potential for false positive tests in this situation. Of the 3388 individuals who were tested, 984 were HIV positive on two consecutive tests, and 29 were considered positive by a tiebreaker (positive on Determine, negative on STAT-PAK, and positive on Uni-Gold). However, when the 29 samples were further tested using qualitative DNA PCR, 14 (48.2%) were HIV negative. Although this study was not primarily designed to assess the validity of rapid HIV tests and thus only a subset of the samples were retested, the findings show a potential for false positive HIV results in the subset of individuals who test positive when a tiebreaker test is used in serial testing. These findings highlight a need for confirmatory testing for this category of individuals.

Potential for false positive HIV test results with the serial rapid HIV testing algorithm

PubMed Central

2012-01-01

Background Rapid HIV tests provide same-day results and are widely used in HIV testing programs in areas with limited personnel and laboratory infrastructure. The Uganda Ministry of Health currently recommends the serial rapid testing algorithm with Determine, STAT-PAK, and Uni-Gold for diagnosis of HIV infection. Using this algorithm, individuals who test positive on Determine, negative to STAT-PAK and positive to Uni-Gold are reported as HIV positive. We conducted further testing on this subgroup of samples using qualitative DNA PCR to assess the potential for false positive tests in this situation. Results Of the 3388 individuals who were tested, 984 were HIV positive on two consecutive tests, and 29 were considered positive by a tiebreaker (positive on Determine, negative on STAT-PAK, and positive on Uni-Gold). However, when the 29 samples were further tested using qualitative DNA PCR, 14 (48.2%) were HIV negative. Conclusion Although this study was not primarily designed to assess the validity of rapid HIV tests and thus only a subset of the samples were retested, the findings show a potential for false positive HIV results in the subset of individuals who test positive when a tiebreaker test is used in serial testing. These findings highlight a need for confirmatory testing for this category of individuals. PMID:22429706

Alcohol calibration of tests measuring skills related to car driving.

PubMed

Jongen, Stefan; Vuurman, Eric; Ramaekers, Jan; Vermeeren, Annemiek

2014-06-01

Medication and illicit drugs can have detrimental side effects which impair driving performance. A drug's impairing potential should be determined by well-validated, reliable, and sensitive tests and ideally be calibrated by benchmark drugs and doses. To date, no consensus has been reached on the issue of which psychometric tests are best suited for initial screening of a drug's driving impairment potential. The aim of this alcohol calibration study is to determine which performance tests are useful to measure drug-induced impairment. The effects of alcohol are used to compare the psychometric quality between tests and as benchmark to quantify performance changes in each test associated with potentially impairing drug effects. Twenty-four healthy volunteers participated in a double-blind, four-way crossover study. Treatments were placebo and three different doses of alcohol leading to blood alcohol concentrations (BACs) of 0.2, 0.5, and 0.8 g/L. Main effects of alcohol were found in most tests. Compared with placebo, performance in the Divided Attention Test (DAT) was significantly impaired after all alcohol doses and performance in the Psychomotor Vigilance Test (PVT) and the Balance Test was impaired with a BAC of 0.5 and 0.8 g/L. The largest effect sizes were found on postural balance with eyes open and mean reaction time in the divided attention and the psychomotor vigilance test. The preferable tests for initial screening are the DAT and the PVT, as these tests were most sensitive to the impairing effects of alcohol and being considerably valid in assessing potential driving impairment.

Investigation on bending failure to characterize crashworthiness of 6xxx-series aluminium sheet alloys with bending-tension test procedure

NASA Astrophysics Data System (ADS)

Henn, Philipp; Liewald, Mathias; Sindel, Manfred

2018-05-01

As lightweight design as well as crash performance are crucial to future car body design, exact material characterisation is important to use materials at their full potential and reach maximum efficiency. Within the scope of this paper, the potential of newly established bending-tension test procedure to characterise material crashworthiness is investigated. In this test setup for the determination of material failure, a buckling-bending test is coupled with a subsequent tensile test. If prior bending load is critical, tensile strength and elongation in the subsequent tensile test are dramatically reduced. The new test procedure therefore offers an applicable definition of failure as the incapacity of energy consumption in subsequent phases of the crash represents failure of a component. In addition to that, the correlation of loading condition with actual crash scenarios (buckling and free bending) is improved compared to three- point bending test. The potential of newly established bending-tension test procedure to characterise material crashworthiness is investigated in this experimental studys on two aluminium sheet alloys. Experimental results are validated with existing ductility characterisation from edge compression test.

Commercial NiMH Cells in LEO Cycling: Thermal Vacuum Life Test Performed for the Floating Potential Probe (FPP)

NASA Technical Reports Server (NTRS)

Darcy, Eric; Strangways, Brad

2003-01-01

Contents include the following: 1. Introduction: What is the (Floating Potential Probe) FPP? Why was NiMH battery selected? Haw well would crimped seal cell performed in long term vacuum exposure? 2. Verification tests: Battery description. Test methods. Results. Main findings. FPP status.

Testing the Test: A Study of PARCC Field Trials in Two School Districts. Policy Brief

ERIC Educational Resources Information Center

Rennie Center for Education Research & Policy, 2015

2015-01-01

The potential use of computer-based assessments has raised concerns from educators, policymakers, and parents about information technology infrastructure in school districts and the preparation of staff and students to use new technologies for assessment purposes, and the potential impact of testing activities on core school functions,…

Introducing "Emotioncy" as a Potential Source of Test Bias: A Mixed Rasch Modeling Study

ERIC Educational Resources Information Center

Pishghadam, Reza; Baghaei, Purya; Seyednozadi, Zahra

2017-01-01

This article attempts to present emotioncy as a potential source of test bias to inform the analysis of test item performance. Emotioncy is defined as a hierarchy, ranging from "exvolvement" (auditory, visual, and kinesthetic) to "involvement" (inner and arch), to emphasize the emotions evoked by the senses. This study…

HAZARD IDENTIFICATION: EFFICIENCY OF SHORT-TERM TESTS IN IDENTIFYING GERM CELL MUTAGENS AND PUTATIVE NONGENOTOXIC CARCINOGENS

EPA Science Inventory

For more than a decade, mutagenicity tests have had a clearly defined role in the identification of potential human mutagens and an ancillary role in the identification of potential human carcinogens. he efficiency of short-term tests in identifying germ cell mutagens has been ex...

77 FR 8258 - Availability of ICCVAM Evaluation Report and Recommendations on the Usefulness and Limitations of...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-02-14

... development of BG1Luc ER TA test method performance standards. ICCVAM assigned the activities a high priority... Vitro Test Methods for Detecting Potential Endocrine Disruptors. Research Triangle Park, NC: National...Final.pdf . ICCVAM. 2003a. ICCVAM Evaluation of In Vitro Test Methods For Detecting Potential Endocrine...

Biochemical methane potential (BMP) tests: Reducing test time by early parameter estimation.

PubMed

Da Silva, C; Astals, S; Peces, M; Campos, J L; Guerrero, L

2018-01-01

Biochemical methane potential (BMP) test is a key analytical technique to assess the implementation and optimisation of anaerobic biotechnologies. However, this technique is characterised by long testing times (from 20 to >100days), which is not suitable for waste utilities, consulting companies or plants operators whose decision-making processes cannot be held for such a long time. This study develops a statistically robust mathematical strategy using sensitivity functions for early prediction of BMP first-order model parameters, i.e. methane yield (B 0 ) and kinetic constant rate (k). The minimum testing time for early parameter estimation showed a potential correlation with the k value, where (i) slowly biodegradable substrates (k≤0.1d -1 ) have a minimum testing times of ≥15days, (ii) moderately biodegradable substrates (0.1

High-Temperature Test Technology

DTIC Science & Technology

1987-03-01

delivery methods are available for a test vehicle (e.g., flatbed )? What potential is there to expand the test area? 4. What provision is there for...Yes[- No-- If "yes," what are the dimensions? What delivery methods are available for a test vehicle (e.g., flatbed )? What potential is there to...or (c) air connections introducing additional convection losses, as required for ia) laminated sheet plastic curing. (b) paper dehydrating. (c) heat

In vitro assessment of skin irritation potential of surfactant-based formulations by using a 3-D skin reconstructed tissue model and cytokine response.

PubMed

Walters, Russel M; Gandolfi, Lisa; Mack, M Catherine; Fevola, Michael; Martin, Katharine; Hamilton, Mathew T; Hilberer, Allison; Barnes, Nicole; Wilt, Nathan; Nash, Jennifer R; Raabe, Hans A; Costin, Gertrude-Emilia

2016-12-01

The personal care industry is focused on developing safe, more efficacious, and increasingly milder products, that are routinely undergoing preclinical and clinical testing before becoming available for consumer use on skin. In vitro systems based on skin reconstructed equivalents are now established for the preclinical assessment of product irritation potential and as alternative testing methods to the classic Draize rabbit skin irritation test. We have used the 3-D EpiDerm™ model system to evaluate tissue viability and primary cytokine interleukin-1α release as a way to evaluate the potential dermal irritation of 224 non-ionic, amphoteric and/or anionic surfactant-containing formulations, or individual raw materials. As part of our testing programme, two representative benchmark materials with known clinical skin irritation potential were qualified through repeated testing, for use as references for the skin irritation evaluation of formulations containing new surfactant ingredients. We have established a correlation between the in vitro screening approach and clinical testing, and are continually expanding our database to enhance this correlation. This testing programme integrates the efforts of global manufacturers of personal care products that focus on the development of increasingly milder formulations to be applied to the skin, without the use of animal testing. 2016 FRAME.

Wave Energy Prize - 1/20th Testing - Sea Potential

DOE Data Explorer

Scharmen, Wesley

2016-09-23

Data from the 1/20th scale testing data completed on the Wave Energy Prize for the Sea Potential team, including the 1/20th scale test plan, raw test data, video, photos, and data analysis results. The top level objective of the 1/20th scale device testing is to obtain the necessary measurements required for determining Average Climate Capture Width per Characteristic Capital Expenditure (ACE) and the Hydrodynamic Performance Quality (HPQ), key metrics for determining the Wave Energy Prize (WEP) winners.

One gravitational potential or two? Forecasts and tests.

PubMed

Bertschinger, Edmund

2011-12-28

The metric of a perturbed Robertson-Walker space-time is characterized by three functions: a scale-factor giving the expansion history and two potentials that generalize the single potential of Newtonian gravity. The Newtonian potential induces peculiar velocities and, from these, the growth of matter fluctuations. Massless particles respond equally to the Newtonian potential and to a curvature potential. The difference of the two potentials, called the gravitational slip, is predicted to be very small in general relativity, but can be substantial in modified gravity theories. The two potentials can be measured, and gravity tested on cosmological scales, by combining weak gravitational lensing or the integrated Sachs-Wolfe effect with galaxy peculiar velocities or clustering.

Towards eliminating systematic errors caused by the experimental conditions in Biochemical Methane Potential (BMP) tests.

PubMed

Strömberg, Sten; Nistor, Mihaela; Liu, Jing

2014-11-01

The Biochemical Methane Potential (BMP) test is increasingly recognised as a tool for selecting and pricing biomass material for production of biogas. However, the results for the same substrate often differ between laboratories and much work to standardise such tests is still needed. In the current study, the effects from four environmental factors (i.e. ambient temperature and pressure, water vapour content and initial gas composition of the reactor headspace) on the degradation kinetics and the determined methane potential were evaluated with a 2(4) full factorial design. Four substrates, with different biodegradation profiles, were investigated and the ambient temperature was found to be the most significant contributor to errors in the methane potential. Concerning the kinetics of the process, the environmental factors' impact on the calculated rate constants was negligible. The impact of the environmental factors on the kinetic parameters and methane potential from performing a BMP test at different geographical locations around the world was simulated by adjusting the data according to the ambient temperature and pressure of some chosen model sites. The largest effect on the methane potential was registered from tests performed at high altitudes due to a low ambient pressure. The results from this study illustrate the importance of considering the environmental factors' influence on volumetric gas measurement in BMP tests. This is essential to achieve trustworthy and standardised results that can be used by researchers and end users from all over the world. Copyright © 2014 Elsevier Ltd. All rights reserved.

Home bowel cancer tests and informed choice--is current information sufficient?

PubMed

Howard, K; Salkeld, G

2003-10-01

To evaluate the type of information that is available to purchasers of home-based bowel cancer test kits. Manufacturers, pharmacies and independent testing programs were contacted to obtain faecal occult blood test (FOBT) kits. State cancer organisations were contacted for information on bowel cancer screening. Information on bowel cancer, the FOBT kit, the testing process and potential benefits and harms of the screening process were assessed using guidelines provided by the UK General Medical Council (GMC). FOBT kits and cancer organisation information provided adequate information on the purpose of screening, the screening process itself and potential benefits, but provided no information concerning uncertainties of screening or potential harms. On the basis of both the UK GMC criteria and patient desires for information, the information available at present falls short of being considered adequate for an informed decision to purchase a home-based FOBT. We must ensure adequate and balanced information is available to redress the present information asymmetry to facilitate informed participation in a potentially valuable public health initiative.

Genetic testing in the epilepsies—Report of the ILAE Genetics Commission

PubMed Central

Ottman, Ruth; Hirose, Shinichi; Jain, Satish; Lerche, Holger; Lopes-Cendes, Iscia; Noebels, Jeffrey L.; Serratosa, José; Zara, Federico; Scheffer, Ingrid E.

2010-01-01

SUMMARY In this report, the International League Against Epilepsy (ILAE) Genetics Commission discusses essential issues to be considered with regard to clinical genetic testing in the epilepsies. Genetic research on the epilepsies has led to the identification of more than 20 genes with a major effect on susceptibility to idiopathic epilepsies. The most important potential clinical application of these discoveries is genetic testing: the use of genetic information, either to clarify the diagnosis in people already known or suspected to have epilepsy (diagnostic testing), or to predict onset of epilepsy in people at risk because of a family history (predictive testing). Although genetic testing has many potential benefits, it also has potential harms, and assessment of these potential benefits and harms in particular situations is complex. Moreover, many treating clinicians are unfamiliar with the types of tests available, how to access them, how to decide whether they should be offered, and what measures should be used to maximize benefit and minimize harm to their patients. Because the field is moving rapidly, with new information emerging practically every day, we present a framework for considering the clinical utility of genetic testing that can be applied to many different syndromes and clinical contexts. Given the current state of knowledge, genetic testing has high0020clinical utility in few clinical contexts, but in some of these it carries implications for daily clinical practice. PMID:20100225

Inoculum selection influences the biochemical methane potential of agro-industrial substrates

PubMed Central

De Vrieze, Jo; Raport, Linde; Willems, Bernard; Verbrugge, Silke; Volcke, Eveline; Meers, Erik; Angenent, Largus T; Boon, Nico

2015-01-01

Obtaining a reliable estimation of the methane potential of organic waste streams in anaerobic digestion, for which a biochemical methane potential (BMP) test is often used, is of high importance. Standardization of this BMP test is required to ensure inter-laboratory repeatability and accuracy of the BMP results. Therefore, guidelines were set out; yet, these do not provide sufficient information concerning origin of and the microbial community in the test inoculum. Here, the specific contribution of the methanogenic community on the BMP test results was evaluated. The biomethane potential of four different substrates (molasses, bio-refinery waste, liquid manure and high-rate activated sludge) was determined by means of four different inocula from full-scale anaerobic digestion plants. A significant effect of the selected inoculum on the BMP result was observed for two out of four substrates. This inoculum effect could be attributed to the abundance of methanogens and a potential inhibiting effect in the inoculum itself, demonstrating the importance of inoculum selection for BMP testing. We recommend the application of granular sludge as an inoculum, because of its higher methanogenic abundance and activity, and protection from bulk solutions, compared with other inocula. PMID:25756301

Study Gradation and Moisture Content of Sand Embankment on Peat Subjected Vibration Potential Liquefaction

NASA Astrophysics Data System (ADS)

Agus Nugroho, Soewignjo; Ika Putra, Agus; Yusa, Muhamad

2018-03-01

In recent years large earthquakes often occur on the island of Sumatra. There is a phenomenon of the damage occurred during the earthquake, one of the effects is a phenomenon of loss of soil strength due to vibration called liquefaction. Some cases of liquefaction occur in some areas in Aceh, Nias Island, Padang and Pariaman. Pekanbaru is located close to the fault area that causes the occurrence of earthquake wave propagation. Pekanbaru are also at risk for geotechnical problems because of earthquake such as liquefaction. Evaluation of liquefaction potential could using by in-situ test and by laboratory test. The laboratory test to evaluation liquefaction potential among which method of experiment shaking table. In this study, liquefaction phenomenon was conducted by creating a physical model of a laboratory scale using a one-way vibration machine, with a review of how big the influence of sand gradation, sand shaped and grain-size, and surface water level in the sand against liquefaction potential. Evaluate of liquefaction potential based on the surface reading of the soil movement, elapsed time for final settlement and an excess pore water dissipation (EPD) during testing. Based on the results of performed test, indicated that fine sand on fully saturated conditions have the potential of maximum settlement for 20.67% and maximum ascend of pore water for 46.67%. This result mean that poorly graded fine sand on fully saturated conditions has more liquefaction potential than medium sand, coarse sand, and well graded sand

Effect of chemical etching and aging in boiling water on the corrosion resistance of Nitinol wires with black oxide resulting from manufacturing process.

PubMed

Shabalovskaya, S; Rondelli, G; Anderegg, J; Simpson, B; Budko, S

2003-07-15

The effect of chemical etching in a HF/HNO(3) acid solution and aging in boiling water on the corrosion resistance of Nitinol wires with black oxide has been evaluated with the use of potentiodynamic, modified potentiostatic ASTM F746, and scratch tests. Scanning-electron microscopy, elemental XPS, and Auger analysis were employed to characterize surface alterations induced by surface treatment and corrosion testing. The effect of aging in boiling water on the temperatures of martensitic transformations and shape recovery was evaluated by means of measuring the wire electroresistance. After corrosion tests, as-received wires revealed uniformly cracked surfaces reminiscent of the stress-corrosion-cracking phenomenon. These wires exhibited negative breakdown potentials in potentiostatic tests and variable breakdown potentials in potentiodynamic tests (- 100 mV to + 400 mV versus SCE). Wires with treated surfaces did not reveal cracking or other traces of corrosion attacks in potentiodynamic tests up to + 900-1400-mV potentials and no pitting after stimulation at + 800 mV in potentiostatic tests. They exhibited corrosion behavior satisfactory for medical applications. Significant improvement of corrosion parameters was observed on the reverse scans in potentiodynamic tests after exposure of treated wires to potentials > 1000 mV. In scratch tests, the prepared surfaces repassivated only at low potentials, comparable to that of stainless steel. Tremendous improvement of the corrosion behavior of treated Nitinol wires is associated with the removal of defect surface material and the growth of stable TiO(2) oxide. The role of precipitates in the corrosion resistance of Nitinol-scratch repassivation capacity in particular-is emphasized in the discussion. Copyright 2003 Wiley Periodicals, Inc. J Biomed Mater Res Part B: Appl Biomater 66B: 331-340, 2003

Identifying failure in a tree network of a parallel computer

DOEpatents

Archer, Charles J.; Pinnow, Kurt W.; Wallenfelt, Brian P.

2010-08-24

Methods, parallel computers, and products are provided for identifying failure in a tree network of a parallel computer. The parallel computer includes one or more processing sets including an I/O node and a plurality of compute nodes. For each processing set embodiments include selecting a set of test compute nodes, the test compute nodes being a subset of the compute nodes of the processing set; measuring the performance of the I/O node of the processing set; measuring the performance of the selected set of test compute nodes; calculating a current test value in dependence upon the measured performance of the I/O node of the processing set, the measured performance of the set of test compute nodes, and a predetermined value for I/O node performance; and comparing the current test value with a predetermined tree performance threshold. If the current test value is below the predetermined tree performance threshold, embodiments include selecting another set of test compute nodes. If the current test value is not below the predetermined tree performance threshold, embodiments include selecting from the test compute nodes one or more potential problem nodes and testing individually potential problem nodes and links to potential problem nodes.

Assessing Practical Intelligence in Business School Admissions: A Supplement to the Graduate Management Admissions Test

ERIC Educational Resources Information Center

Hedlund, Jennifer; Wilt, Jeanne M.; Nebel, Kristina L.; Ashford, Susan J.; Sternberg, Robert J.

2006-01-01

The Graduate Management Admission Test (GMAT) is the most widely used measure of managerial potential in MBA admissions. GMAT scores, although predictive of grades in business school, leave much of the variance in graduate school performance unexplained. The GMAT also produces disparities in test scores between groups, generating the potential for…

A Comparison of Validity Rates between Paper-and-Pencil and Computerized Testing with the MMPI-2

ERIC Educational Resources Information Center

Blazek, Nicole L.; Forbey, Johnathan D.

2011-01-01

Although the use of computerized testing in psychopathology assessment has increased in recent years, limited research has examined the impact of this format in terms of potential differences in test validity rates. The current study explores potential differences in the rates of valid and invalid Minnesota Multiphasic Personality Inventory--2…

The Influence of Drug Testing Attributes, Participation, and Personality on Potential Applicant's Attitudes and Job Pursuit Intentions.

ERIC Educational Resources Information Center

Stoffey, Ronald W.

Researchers are increasingly aware of the importance of job applicants' reactions to the personnel selection process. This study examines three variables in connection with drug testing policies: (1) the potential applicant's reactions to two different drug testing policies which varied in terms of drug policy characteristics and their impact on…

Identifying High Academic Potential in Australian Aboriginal Children Using Dynamic Testing

ERIC Educational Resources Information Center

Chaffey, Graham W.; Bailey, Stan B.; Vine, Ken W.

2015-01-01

The primary purpose of this study was to determine the effectiveness of dynamic testing as a method for identifying high academic potential in Australian Aboriginal children. The 79 participating Aboriginal children were drawn from Years 3-5 in rural schools in northern New South Wales. The dynamic testing method used in this study involved a…

A physical action potential generator: design, implementation and evaluation.

PubMed

Latorre, Malcolm A; Chan, Adrian D C; Wårdell, Karin

2015-01-01

The objective was to develop a physical action potential generator (Paxon) with the ability to generate a stable, repeatable, programmable, and physiological-like action potential. The Paxon has an equivalent of 40 nodes of Ranvier that were mimicked using resin embedded gold wires (Ø = 20 μm). These nodes were software controlled and the action potentials were initiated by a start trigger. Clinically used Ag-AgCl electrodes were coupled to the Paxon for functional testing. The Paxon's action potential parameters were tunable using a second order mathematical equation to generate physiologically relevant output, which was accomplished by varying the number of nodes involved (1-40 in incremental steps of 1) and the node drive potential (0-2.8 V in 0.7 mV steps), while keeping a fixed inter-nodal timing and test electrode configuration. A system noise floor of 0.07 ± 0.01 μV was calculated over 50 runs. A differential test electrode recorded a peak positive amplitude of 1.5 ± 0.05 mV (gain of 40x) at time 196.4 ± 0.06 ms, including a post trigger delay. The Paxon's programmable action potential like signal has the possibility to be used as a validation test platform for medical surface electrodes and their attached systems.

Slow positron beam generator for lifetime studies

NASA Technical Reports Server (NTRS)

Singh, Jag J. (Inventor); Eftekhari, Abe (Inventor); St.clair, Terry L. (Inventor)

1991-01-01

A slow positron beam generator uses a conductive source residing between two test films. Moderator pieces are placed next to the test film on the opposite side of the conductive source. A voltage potential is applied between the moderator pieces and the conductive source. Incident energetic positrons: (1) are emitted from the conductive source; (2) are passed through test film; and (3) isotropically strike moderator pieces before diffusing out of the moderator pieces as slow positrons, respectively. The slow positrons diffusing out of moderator pieces are attracted to the conductive source which is held at an appropriate potential below the moderator pieces. The slow positrons have to pass through the test films before reaching the conductive source. A voltage is adjusted so that the potential difference between the moderator pieces and the conductive source forces the positrons to stop in the test films. Measurable annihilation radiation is emitted from the test film when positrons annihilate (combine) with electrons in the test film.

Anaerobic hydrolysis and acidification of organic substrates: determination of anaerobic hydrolytic potential.

PubMed

Rajagopal, Rajinikanth; Béline, Fabrice

2011-05-01

This study aimed to develop a biochemical-test mainly to evaluate the hydrolytic-potential of different substrates and to apply this test to characterize various organic substrates. Outcome of this study can be used for optimization of the WWTPs through enhancement of N/P removal or anaerobic digestion. Out of four series of batch experiments, the first two tests were conducted to determine the optimal operating conditions (test duration, inoculum-ratio etc.) for the hydrolytic-potential test using secondary and synthetically-prepared sludges. Based on the results (generation of CODs, pH and VFA), test duration was fixed between 6 and 7d allowing to attain maximum hydrolysis and to avoid methanogenesis. Effect of inoculum-ratios on acid fermentation of sludge was not significantly noticed. Using this methodology, third and fourth tests were performed to characterize various organic substrates namely secondary, pre-treated sludge, pig and two different cattle slurries. VFA production was shown to be substantially dependent on substrates types. Copyright © 2011 Elsevier Ltd. All rights reserved.

Potential benefits of magnetic suspension and balance systems

NASA Technical Reports Server (NTRS)

Lawing, Pierce L.; Dress, David A.; Kilgore, Robert A.

1987-01-01

The potential of Magnetic Suspension and Balance Systems (MSBS) to improve conventional wind tunnel testing techniques is discussed. Topics include: elimination of model geometry distortion and support interference to improve the measurement accuracy of aerodynamic coefficients; removal of testing restrictions due to supports; improved dynamic stability data; and stores separation testing. Substantial increases in wind tunnel productivity are anticipated due to the coalescence of these improvements. Specific improvements in testing methods for missiles, helicopters, fighter aircraft, twin fuselage transports and bombers, state separation, water tunnels, and automobiles are also forecast. In a more speculative vein, new wind tunnel test techniques are envisioned as a result of applying MSBS, including free-flight computer trajectories in the test section, pilot-in-the-loop and designer-in-the-loop testing, shipboard missile launch simulation, and optimization of hybrid hypersonic configurations. Also addressed are potential applications of MSBS to such diverse technologies as medical research and practice, industrial robotics, space weaponry, and ore processing in space.

77 FR 59209 - Information Collection Activities: Oil and Gas Production Requirements; Proposed Collection...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-09-26

... & 60[deg]F''. We use the information in Form BSEE-0126, Well Potential Test Report, for reservoir... necessary for certain oil and gas completions. The information obtained from the well potential test is...

Testing ocular irritancy in vitro with the silicon microphysiometer.

PubMed

Bruner, L H; Miller, K R; Owicki, J C; Parce, J W; Muir, V C

1991-01-01

The silicon microphysiometer, an instrument based on the light-addressable potentiometric sensor, was evaluated as an in vitro alternative for assessing ocular irritancy potential. It indirectly and non-invasively measures cell metabolism by determining the rate of acid metabolite production from cells, in this case human epidermal keratinocytes, placed inside the microphysiometer chamber. The 17 materials used for the evaluation included bar soaps, a liquid hand soap, shampoos, dishwashing liquids, laundry detergents, a fabric softener and several single chemicals. All materials tested were in liquid form. The in vivo irritancy potential of the materials was obtained from historical data using the rabbit low-volume eye test. There was a positive correlation between the in vivo irritancy potential of the test materials and the concentration of test material that decreased the acidification rate of cells by 50% (MRD(50); r = 0.86, P < 0.0001). Preliminary studies suggest other endpoints obtainable from the system may also provide useful information for making ocular safety assessments. Because the method is non-invasive, it is possible to determine whether cells recover from a treatment with the test material. The metabolic rate of the cells also increases at sub-inhibitory concentrations of some of the test materials. Because of the good correlation between the in vivo and in vitro data, the ease with which test materials can be applied to the system, and the multiple endpoints available from the system, it holds great potential as a useful in vitro alternative for ocular safety testing.

Evaluation of select neurophysiological, clinical and psychological tests for burning mouth syndrome.

PubMed

Mendak-Ziółko, Magdalena; Konopka, Tomasz; Bogucki, Zdzisław Artur

2012-09-01

The objective of this study was to identify, among an array of potential risk factors for burning mouth syndrome (BMS), those that are potentially the most significant in the development of the disease. Sixty-three participants, divided into group I (with BMS: 33 patients ages 41 to 82 years [mean age: 61.5 ± 9.4]) and group II (without BMS: 30 healthy volunteers ages 42-83 years [mean age: 60.5 ± 10.5]) were studied. All underwent a dental examination and psychological tests. Neurological tests (neurophysiological test, electroneurography, and tests of the autonomic nervous system) were performed. Mean parameters were analyzed by Student t test, Kruskal-Wallis test, and χ(2) test, and multifactor analysis was performed with logistic regression and by calculating the odds ratio. In the logistic regression test, 3 factors were significant in the etiopathogenesis of BMS: a value more than 39 μV for the amplitude of the positive peak of the potential induced by stimulating the trigeminal nerve on the left side (P2-L); a value above 5.96 ms for the latency of wave V of the brainstem auditory evoked potentials on the right side (V-R); and a value over 2.35 ms for the latency of the sensory ulnar nerve response. The BMS sufferer was characterized as having mild sensory and autonomic small fiber neuropathy with concomitant central disorders. Copyright © 2012 Elsevier Inc. All rights reserved.

Learning Potential Among the Moderately and Severely Retarded. Studies in Learning Potential, Volume 3, Number 52.

ERIC Educational Resources Information Center

Hamilton, James L.; Budoff, Milton

The study investigated the feasibility of M. Budoff and M. Friedman's (1964) learning potential paradigm as an assessment approach with 40 moderately and severely mentally retarded persons (aged 12 to 22 years). Ss were tested three times: initially, after one week, and after one month with a match-to-sample block design test. Twenty of the Ss…

A simple screening test for the detection of metallo-β-lactamase-producing Pseudomonas aeruginosa and Acinetobacter in a tertiary care hospital.

PubMed

Wan Nor Amilah, W A W; Noor Izani, N J; Ng, W K; Ashraful Haq, J

2012-12-01

Clinical utilization of carbapenems remains under threat with the emergence of acquired carbapenemase-producing bacteria, particularly metallo-β-lactamases (MBL). Rapid detection of MBL-producing Gram-negative bacilli is essential to prevent their widespread dissemination. However, no standardized detection method is available for routine laboratory use. The purpose of the study was to evaluate a chelating-agent based double disk synergic test and disk potentiation test for MBL-producing strain detection and to determine the isolation rate of MBL-producing Pseudomonas aeruginosa and Acinetobacter from clinical samples in our tertiary teaching hospital. A total of 22 and 66 imipenem-resistant P. aeruginosa and Acinetobacter isolates respectively were tested with ceftazidime (CAZ) disk by modified double disk synergic test and disk potentiation test using ethylenediaminetetraacetic acid (EDTA) and 2-mercaptopropionic acid (as chelating agents) to detect MBL production. The tests were compared with EDTA-phenanthroline-imipenem (EPI) microdilution MIC test as gold standard. MBL positive strains were detected in 17 (77.3%) P. aeruginosa and 2 (3.5%) Acinetobacter isolates. The disk potentiation test with 2-mercaptopropionic acid (2-MPA) dilution of 1:12 provided the most acceptable sensitivities and specificities (88.2% sensitivity and 100% specificity in P. aeruginosa; 100% sensitivity and specificity in Acinetobacter) compared to other screening methods used in this study. This study provided useful information on the local prevalence of MBL-producing P. aeruginosa and Acinetobacter in our hospital. Disc potentiation test with CAZ/2-MPA disc appears to be reliable and convenient MBL detection method in the routine clinical laboratory.

The extended Lennard-Jones potential energy function: A simpler model for direct-potential-fit analysis

NASA Astrophysics Data System (ADS)

Hajigeorgiou, Photos G.

2016-12-01

An analytical model for the diatomic potential energy function that was recently tested as a universal function (Hajigeorgiou, 2010) has been further modified and tested as a suitable model for direct-potential-fit analysis. Applications are presented for the ground electronic states of three diatomic molecules: oxygen, carbon monoxide, and hydrogen fluoride. The adjustable parameters of the extended Lennard-Jones potential model are determined through nonlinear regression by fits to calculated rovibrational energy term values or experimental spectroscopic line positions. The model is shown to lead to reliable, compact and simple representations for the potential energy functions of these systems and could therefore be classified as a suitable and attractive model for direct-potential-fit analysis.

An Empirical Investigation of the Potential Impact of Item Misfit on Test Scores. Research Report. ETS RR-17-60

ERIC Educational Resources Information Center

Kim, Sooyeon; Robin, Frederic

2017-01-01

In this study, we examined the potential impact of item misfit on the reported scores of an admission test from the subpopulation invariance perspective. The target population of the test consisted of 3 major subgroups with different geographic regions. We used the logistic regression function to estimate item parameters of the operational items…

High speed turboprops for executive aircraft, potential and recent test results

NASA Technical Reports Server (NTRS)

Mikkelson, D. C.; Mitchell, G. A.

1980-01-01

Four high speed propeller models were designed and tested in an 8x6 foot wind tunnel in order to evaluate the potential of advanced propeller technology. Results from these tests show that the combination of: increased blade number, aerodynamically integrated propeller/nacelles, reduced blade thickness, spinner area ruling, and blade sweep are important in achieving high propeller efficiency at the high cruise speeds.

Characterization of new eye drops with choline salicylate and assessment of their irritancy by in vitro short time exposure tests.

PubMed

Wroblewska, Katarzyna; Kucinska, Małgorzata; Murias, Marek; Lulek, Janina

2015-09-01

The aim of our study was to examine the irritation potential of new eye drops containing 2% choline salicylate (CS) as an active pharmaceutical ingredient (API) and various polymers increasing eye drop viscosity (hydroxyethylcellulose, hydroxypropyl methylcellulose, methylcellulose, polyvinyl alcohol, polyvinylpyrrolidone). The standard method for assessing the potential of irritating substances has been the Draize rabbit eye test. However the European Centre for Validation of Alternative Methods and the Coordinating Committee for Validation of Alternative Methods recommend, short time exposure (STE) in vitro tests as an alternative method for assessing eye irritation. The eye irritation potential was determined using cytotoxicity test methods for rabbit corneal cell line (SIRC) after 5 min exposure. The viability of cells was determined using two cytotoxicity assays: MTT and Neutral Red Uptake. According to the irritation rankings for the short time exposure test, all tested eye drops are classified as non-irritating (cell viability >70%).

Characterization of new eye drops with choline salicylate and assessment of their irritancy by in vitro short time exposure tests

PubMed Central

Wroblewska, Katarzyna; Kucinska, Małgorzata; Murias, Marek; Lulek, Janina

2014-01-01

The aim of our study was to examine the irritation potential of new eye drops containing 2% choline salicylate (CS) as an active pharmaceutical ingredient (API) and various polymers increasing eye drop viscosity (hydroxyethylcellulose, hydroxypropyl methylcellulose, methylcellulose, polyvinyl alcohol, polyvinylpyrrolidone). The standard method for assessing the potential of irritating substances has been the Draize rabbit eye test. However the European Centre for Validation of Alternative Methods and the Coordinating Committee for Validation of Alternative Methods recommend, short time exposure (STE) in vitro tests as an alternative method for assessing eye irritation. The eye irritation potential was determined using cytotoxicity test methods for rabbit corneal cell line (SIRC) after 5 min exposure. The viability of cells was determined using two cytotoxicity assays: MTT and Neutral Red Uptake. According to the irritation rankings for the short time exposure test, all tested eye drops are classified as non-irritating (cell viability >70%). PMID:27134543

Informed choice in direct-to-consumer genetic testing (DTCGT) websites: a content analysis of benefits, risks, and limitations.

PubMed

Singleton, Amanda; Erby, Lori Hamby; Foisie, Kathryn V; Kaphingst, Kimberly A

2012-06-01

An informed choice about health-related direct-to-consumer genetic testing (DTCGT) requires knowledge of potential benefits, risks, and limitations. To understand the information that potential consumers of DTCGT services are exposed to on company websites, we conducted a content analysis of 23 health-related DTCGT websites. Results revealed that benefit statements outweighed risk and limitation statements 6 to 1. The most frequently described benefits were: 1) disease prevention, 2) consumer education, 3) personalized medical recommendations, and 4) the ability to make health decisions. Thirty-five percent of websites also presented at least one risk of testing. Seventy-eight percent of websites mentioned at least one limitation of testing. Based on this information, potential consumers might get an inaccurate picture of genetic testing which could impact their ability to make an informed decision. Practices that enhance the presentation of balanced information on DTCGT company websites should be encouraged.

Pitting Initiation and Propagation of X70 Pipeline Steel Exposed to Chloride-Containing Environments

PubMed Central

Yang, Zixuan; Kan, Bo; Li, Jinxu; Su, Yanjing; Qiao, Lijie; Volinsky, Alex A.

2017-01-01

Inclusion-induced pitting initiation mechanisms in X70 steel were investigated by scanning electron microscopy, scanning Kelvin probe force microscopy (SKPFM), immersion and electrochemical polarization tests in chloride-containing ion solutions. There are three inclusion types in the X70 steel. Corrosion test results indicated that pitting corrosion resistance of type A inclusion < type C inclusion < type B inclusion, i.e., (Mn, Ca)S < matrix < (Al, Ca)O. SKPFM test results show that the type A inclusion exhibited both lower and higher potentials than the matrix, while the type B inclusion exhibited higher potential than the matrix. The corrosion test and the SKPFM potential test results are consistent. Potentiodynamic polarization results indicate that the type A and C are active inclusions, while the type B is an inactive inclusion. Three kinds of possible mechanisms of inclusion-induced pitting corrosion are established for the X70 steel. PMID:28902156

Clinical Applications for EPs in the ICU.

PubMed

Koenig, Matthew A; Kaplan, Peter W

2015-12-01

In critically ill patients, evoked potential (EP) testing is an important tool for measuring neurologic function, signal transmission, and secondary processing of sensory information in real time. Evoked potential measures conduction along the peripheral and central sensory pathways with longer-latency potentials representing more complex thalamocortical and intracortical processing. In critically ill patients with limited neurologic exams, EP provides a window into brain function and the potential for recovery of consciousness. The most common EP modalities in clinical use in the intensive care unit include somatosensory evoked potentials, brainstem auditory EPs, and cortical event-related potentials. The primary indications for EP in critically ill patients are prognostication in anoxic-ischemic or traumatic coma, monitoring for neurologic improvement or decline, and confirmation of brain death. Somatosensory evoked potentials had become an important prognostic tool for coma recovery, especially in comatose survivors of cardiac arrest. In this population, the bilateral absence of cortical somatosensory evoked potentials has nearly 100% specificity for death or persistent vegetative state. Historically, EP has been regarded as a negative prognostic test, that is, the absence of cortical potentials is associated with poor outcomes while the presence cortical potentials are prognostically indeterminate. In recent studies, the presence of middle-latency and long-latency potentials as well as the amplitude of cortical potentials is more specific for good outcomes. Event-related potentials, particularly mismatch negativity of complex auditory patterns, is emerging as an important positive prognostic test in patients under comatose. Multimodality predictive algorithms that combine somatosensory evoked potentials, event-related potentials, and clinical and radiographic factors are gaining favor for coma prognostication.

Identifying potential kidney donors using social networking web sites.

PubMed

Chang, Alexander; Anderson, Emily E; Turner, Hang T; Shoham, David; Hou, Susan H; Grams, Morgan

2013-01-01

Social networking sites like Facebook may be a powerful tool for increasing rates of live kidney donation. They allow for wide dissemination of information and discussion and could lessen anxiety associated with a face-to-face request for donation. However, sparse data exist on the use of social media for this purpose. We searched Facebook, the most popular social networking site, for publicly available English-language pages seeking kidney donors for a specific individual, abstracting information on the potential recipient, characteristics of the page itself, and whether potential donors were tested. In the 91 pages meeting inclusion criteria, the mean age of potential recipients was 37 (range: 2-69); 88% were US residents. Other posted information included the individual's photograph (76%), blood type (64%), cause of kidney disease (43%), and location (71%). Thirty-two percent of pages reported having potential donors tested, and 10% reported receiving a live-donor kidney transplant. Those reporting donor testing shared more potential recipient characteristics, provided more information about transplantation, and had higher page traffic. Facebook is already being used to identify potential kidney donors. Future studies should focus on how to safely, ethically, and effectively use social networking sites to inform potential donors and potentially expand live kidney donation. © 2013 John Wiley & Sons A/S.

Identifying Potential Kidney Donors Using Social Networking Websites

PubMed Central

Chang, Alexander; Anderson, Emily E.; Turner, Hang T.; Shoham, David; Hou, Susan H.; Grams, Morgan

2013-01-01

Social networking sites like Facebook may be a powerful tool for increasing rates of live kidney donation. They allow for wide dissemination of information and discussion, and could lessen anxiety associated with a face-to-face request for donation. However, sparse data exist on the use of social media for this purpose. We searched Facebook, the most popular social networking site, for publicly available English-language pages seeking kidney donors for a specific individual, abstracting information on the potential recipient, characteristics of the page itself, and whether potential donors were tested. In the 91 pages meeting inclusion criteria, the mean age of potential recipients was 37 (range: 2–69); 88% were U.S. residents. Other posted information included the individual’s photograph (76%), blood type (64%), cause of kidney disease (43%), and location (71%). Thirty-two percent of pages reported having potential donors tested, and 10% reported receiving a live donor kidney transplant. Those reporting donor testing shared more potential recipient characteristics, provided more information about transplantation, and had higher page traffic. Facebook is already being used to identify potential kidney donors. Future studies should focus on how to safely, ethically, and effectively use social networking sites to inform potential donors and potentially expand live kidney donation. PMID:23600791

Foam property tests to evaluate the potential for longwall shield dust control.

PubMed

Reed, W R; Beck, T W; Zheng, Y; Klima, S; Driscoll, J

2018-01-01

Tests were conducted to determine properties of four foam agents for their potential use in longwall mining dust control. Foam has been tried in underground mining in the past for dust control and is currently being reconsidered for use in underground coal longwall operations in order to help those operations comply with the Mine Safety and Health Administration's lower coal mine respirable dust standard of 1.5 mg/m 3 . Foams were generated using two different methods. One method used compressed air and water pressure to generate foam, while the other method used low-pressure air generated by a blower and water pressure using a foam generator developed by the U.S. National Institute for Occupational Safety and Health. Foam property tests, consisting of a foam expansion ratio test and a water drainage test, were conducted to classify foams. Compressed-air-generated foams tended to have low expansion ratios, from 10 to 19, with high water drainage. Blower-air-generated foams had higher foam expansion ratios, from 30 to 60, with lower water drainage. Foams produced within these ranges of expansion ratios are stable and potentially suitable for dust control. The test results eliminated two foam agents for future testing because they had poor expansion ratios. The remaining two foam agents seem to have properties adequate for dust control. These material property tests can be used to classify foams for their potential use in longwall mining dust control.

Foam property tests to evaluate the potential for longwall shield dust control

PubMed Central

Reed, W.R.; Beck, T.W.; Zheng, Y.; Klima, S.; Driscoll, J.

2018-01-01

Tests were conducted to determine properties of four foam agents for their potential use in longwall mining dust control. Foam has been tried in underground mining in the past for dust control and is currently being reconsidered for use in underground coal longwall operations in order to help those operations comply with the Mine Safety and Health Administration’s lower coal mine respirable dust standard of 1.5 mg/m3. Foams were generated using two different methods. One method used compressed air and water pressure to generate foam, while the other method used low-pressure air generated by a blower and water pressure using a foam generator developed by the U.S. National Institute for Occupational Safety and Health. Foam property tests, consisting of a foam expansion ratio test and a water drainage test, were conducted to classify foams. Compressed-air-generated foams tended to have low expansion ratios, from 10 to 19, with high water drainage. Blower-air-generated foams had higher foam expansion ratios, from 30 to 60, with lower water drainage. Foams produced within these ranges of expansion ratios are stable and potentially suitable for dust control. The test results eliminated two foam agents for future testing because they had poor expansion ratios. The remaining two foam agents seem to have properties adequate for dust control. These material property tests can be used to classify foams for their potential use in longwall mining dust control. PMID:29416179

Critical overview of applications of genetic testing in sport talent identification.

PubMed

Roth, Stephen M

2012-12-01

Talent identification for future sport performance is of paramount interest for many groups given the challenges of finding and costs of training potential elite athletes. Because genetic factors have been implicated in many performance- related traits (strength, endurance, etc.), a natural inclination is to consider the addition of genetic testing to talent identification programs. While the importance of genetic factors to sport performance is generally not disputed, whether genetic testing can positively inform talent identification is less certain. The present paper addresses the science behind the genetic tests that are now commercially available (some under patent protection) and aimed at predicting future sport performance potential. Also discussed are the challenging ethical issues that emerge from the availability of these tests. The potential negative consequences associated with genetic testing of young athletes will very likely outweigh any positive benefit for sport performance prediction at least for the next several years. The paper ends by exploring the future possibilities for genetic testing as the science of genomics in sport matures over the coming decade(s).

Active control of spacecraft potentials at geosynchronous orbit

NASA Technical Reports Server (NTRS)

Goldstein, R.; Deforest, S. E.

1976-01-01

Tests have been conducted concerning the active control of the potentials of the geosynchronous satellites ATS-5 and ATS-6. The ATS-5 tests show that a simple electron emitter can be used to reduce the magnitude of the potential of a spacecraft which has been charged negatively by the environment. The ATS-6 ion thruster had also a pronounced effect on the potential barrier. In this case, the flux of high-energy primary ions and of low-charge exchange ions produces a space-charge neutralization effect which the electron gun alone cannot achieve.

Neuronal models for evaluation of proliferation in vitro using high content screening

EPA Science Inventory

In vitro test methods can provide a rapid approach for the screening of large numbers of chemicals for their potential to produce toxicity (hazard identification). In order to identify potential developmental neurotoxicants, a battery of in vitro tests for neurodevelopmental proc...

Penicillin skin testing: potential implications for antimicrobial stewardship.

PubMed

Unger, Nathan R; Gauthier, Timothy P; Cheung, Linda W

2013-08-01

As the progression of multidrug-resistant organisms and lack of novel antibiotics move us closer toward a potential postantibiotic era, it is paramount to preserve the longevity of current therapeutic agents. Moreover, novel interventions for antimicrobial stewardship programs are integral to combating antimicrobial resistance worldwide. One unique method that may decrease the use of second-line antibiotics (e.g., fluoroquinolones, vancomycin) while facilitating access to a preferred β-lactam regimen in numerous health care settings is a penicillin skin test. Provided that up to 10% of patients have a reported penicillin allergy, of whom ~10% have true IgE-mediated hypersensitivity, significant potential exists to utilize a penicillin skin test to safely identify those who may receive penicillin or a β-lactam antibiotic. In this article, we provide information on the background, associated costs, currently available literature, pharmacists' role, antimicrobial stewardship implications, potential barriers, and misconceptions, as well as future directions associated with the penicillin skin test. © 2013 Pharmacotherapy Publications, Inc.

Environmental Quality Research, Use of Unicellular Algae for Evaluation of Potential Aquatic Contaminants

DTIC Science & Technology

1978-11-01

bioassays to determine the toxic and/or biostimulating effects of hydrazine and methylated hydrazines in various freshwater and marine aquatic environments...Table 2. TABLE 2 COMPOUNDS TESTED AND TEST CONDITIONS OF 1976/77 BIOASSAYS COMPOUND TEST CONDITIONS Type of Water Nutrient Level Hydrazine Freshwater ...AMRL-TR-78-86 ENVIRONMENTAL QUALITY RESEARCH, USE OF UNICELLULAR ALGAE FOR EVALUATION OF POTENTIAL AQUATIC CONTAMINANTS Third Annual Report JAN

Towards eliminating systematic errors caused by the experimental conditions in Biochemical Methane Potential (BMP) tests

DOE Office of Scientific and Technical Information (OSTI.GOV)

Strömberg, Sten, E-mail: sten.stromberg@biotek.lu.se; Nistor, Mihaela, E-mail: mn@bioprocesscontrol.com; Liu, Jing, E-mail: jing.liu@biotek.lu.se

Highlights: • The evaluated factors introduce significant systematic errors (10–38%) in BMP tests. • Ambient temperature (T) has the most substantial impact (∼10%) at low altitude. • Ambient pressure (p) has the most substantial impact (∼68%) at high altitude. • Continuous monitoring of T and p is not necessary for kinetic calculations. - Abstract: The Biochemical Methane Potential (BMP) test is increasingly recognised as a tool for selecting and pricing biomass material for production of biogas. However, the results for the same substrate often differ between laboratories and much work to standardise such tests is still needed. In the currentmore » study, the effects from four environmental factors (i.e. ambient temperature and pressure, water vapour content and initial gas composition of the reactor headspace) on the degradation kinetics and the determined methane potential were evaluated with a 2{sup 4} full factorial design. Four substrates, with different biodegradation profiles, were investigated and the ambient temperature was found to be the most significant contributor to errors in the methane potential. Concerning the kinetics of the process, the environmental factors’ impact on the calculated rate constants was negligible. The impact of the environmental factors on the kinetic parameters and methane potential from performing a BMP test at different geographical locations around the world was simulated by adjusting the data according to the ambient temperature and pressure of some chosen model sites. The largest effect on the methane potential was registered from tests performed at high altitudes due to a low ambient pressure. The results from this study illustrate the importance of considering the environmental factors’ influence on volumetric gas measurement in BMP tests. This is essential to achieve trustworthy and standardised results that can be used by researchers and end users from all over the world.« less

Nickel release from surgical instruments and operating room equipment.

PubMed

Boyd, Anne H; Hylwa, Sara A

2018-04-15

Background There has been no systematic study assessing nickel release from surgical instruments and equipment used within the operating suite. This equipment represents important potential sources of exposure for nickel-sensitive patients and hospital staff. To investigate nickel release from commonly used surgical instruments and operating room equipment. Using the dimethylglyoxime nickel spot test, a variety of surgical instruments and operating room equipment were tested for nickel release at our institution. Of the 128 surgical instruments tested, only 1 was positive for nickel release. Of the 43 operating room items tested, 19 were positive for nickel release, 7 of which have the potential for direct contact with patients and/or hospital staff. Hospital systems should be aware of surgical instruments and operating room equipment as potential sources of nickel exposure.

How to assess the mutagenic potential of cosmetic products without animal tests?

PubMed

Speit, Günter

2009-08-01

Animal experiments (in vivo tests) currently play a key role in genotoxicity testing. Results from in vivo tests are, in many cases, decisive for the assessment of a mutagenic potential of a test compound. The Seventh Amendment to the European Cosmetics Directive will, however, ban the European marketing of cosmetic/personal care products that contain ingredients that have been tested in animal experiments. If genotoxicity testing is solely based on the currently established in vitro tests, the attrition rate for chemicals used in cosmetic products will greatly increase due to irrelevant positive in vitro test results. There is urgent need for new and/or improved in vitro genotoxicity tests and for modified test strategies. Test strategies should consider all available information on chemistry of the test substance/the chemical class (e.g. SAR, metabolic activation and dermal adsorption). Test protocols for in vitro genotoxicity tests should be sensitive and robust enough to ensure that negative results can be accepted with confidence. It should be excluded that positive in vitro test results are due to high cytotoxicity or secondary genotoxic effects which may be thresholded and/or only occur under in vitro test conditions. Consequently, further research is needed to establish the nature of thresholds in in vitro assays and to determine the potential for incorporation of mode of action data into future risk assessments. New/improved tests have to be established and validated, considering the use of (metabolically competent) primary (skin) cells, 3D skin models and cells with defined capacity for metabolic activation (e.g. genetically engineered cell lines). The sensitivity and specificity of new and improved genotoxicity tests has to be determined by testing a battery of genotoxic and non-genotoxic chemicals. New or adapted international guidelines will be needed for these tests. The establishment of such a new genotoxicity testing strategy will take time and the new in vitro genotoxicity testing will become much more complex and will require greater mechanistic understanding to build a weight of evidence decision, which will be demanding and time-consuming. At present, no validated alternative methods for the follow-up of positive results from the standard genotoxicity battery are available and an appropriate evaluation of the mutagenic potential of cosmetic ingredients without animal experiments is therefore not possible in many cases.

Exploratory evaluation of ceramics for automobile thermal reactors

NASA Technical Reports Server (NTRS)

Stone, P. L.; Blankenship, C. P.

1972-01-01

An exploratory evaluation of ceramics for automobile thermal reactors was conducted. Potential ceramic materials were evaluated in several reactor designs using both engine dynamometer and vehicle road tests. Silicon carbide contained in a corrugated metal support structure exhibited the best performance lasting over 800 hours in engine dynamometer tests and over 15,000 miles (24,200 km) of vehicle road tests. Reactors containing glass-ceramic components did not perform as well as silicon carbide. But the glass-ceramics still offer good potential for reactor use. The results of this study are considered to be a reasonable demonstration of the potential use of ceramics in thermal reactors.

Data base management study

NASA Technical Reports Server (NTRS)

1976-01-01

Data base management techniques and applicable equipment are described. Recommendations which will assist potential NASA data users in selecting and using appropriate data base management tools and techniques are presented. Classes of currently available data processing equipment ranging from basic terminals to large minicomputer systems were surveyed as they apply to the needs of potential SEASAT data users. Cost and capabilities projections for this equipment through 1985 were presented. A test of a typical data base management system was described, as well as the results of this test and recommendations to assist potential users in determining when such a system is appropriate for their needs. The representative system tested was UNIVAC's DMS 1100.

Test-Enhanced Learning: The Potential for Testing to Promote Greater Learning in Undergraduate Science Courses

PubMed Central

Brame, Cynthia J.; Biel, Rachel

2015-01-01

Testing within the science classroom is commonly used for both formative and summative assessment purposes to let the student and the instructor gauge progress toward learning goals. Research within cognitive science suggests, however, that testing can also be a learning event. We present summaries of studies that suggest that repeated retrieval can enhance long-term learning in a laboratory setting; various testing formats can promote learning; feedback enhances the benefits of testing; testing can potentiate further study; and benefits of testing are not limited to rote memory. Most of these studies were performed in a laboratory environment, so we also present summaries of experiments suggesting that the benefits of testing can extend to the classroom. Finally, we suggest opportunities that these observations raise for the classroom and for further research. PMID:25999314

WITHIN-SESSION CHANGES IN PEAK N160 AMPLITUDE OF FLASH EVOKED POTENTIALS IN RATS

EPA Science Inventory

The negative peak occurring approximately 160 msec after stimulation (peak N 160) flash evoked potentials (FEPS) of rats changes with repeated testing. abituation, sensitization, and arousal have all been invoked to explain these changes, but few studies have directly tested thes...

Estimating and Testing the Sources of Evoked Potentials in the Brain.

ERIC Educational Resources Information Center

Huizenga, Hilde M.; Molenaar, Peter C. M.

1994-01-01

The source of an event-related brain potential (ERP) is estimated from multivariate measures of ERP on the head under several mathematical and physical constraints on the parameters of the source model. Statistical aspects of estimation are discussed, and new tests are proposed. (SLD)

42 CFR 482.27 - Condition of participation: Laboratory services.

Code of Federal Regulations, 2012 CFR

2012-10-01

... infectious blood and blood components—(1) Potentially human immunodeficiency virus (HIV) infectious blood and blood components. Potentially HIV infectious blood and blood components are prior collections from a donor— (i) Who tested negative at the time of donation but tests reactive for evidence of HIV infection...

42 CFR 482.27 - Condition of participation: Laboratory services.

Code of Federal Regulations, 2010 CFR

2010-10-01

... infectious blood and blood components—(1) Potentially human immunodeficiency virus (HIV) infectious blood and blood components. Potentially HIV infectious blood and blood components are prior collections from a donor— (i) Who tested negative at the time of donation but tests reactive for evidence of HIV infection...

42 CFR 482.27 - Condition of participation: Laboratory services.

Code of Federal Regulations, 2013 CFR

2013-10-01

... infectious blood and blood components—(1) Potentially human immunodeficiency virus (HIV) infectious blood and blood components. Potentially HIV infectious blood and blood components are prior collections from a donor— (i) Who tested negative at the time of donation but tests reactive for evidence of HIV infection...

42 CFR 482.27 - Condition of participation: Laboratory services.

Code of Federal Regulations, 2014 CFR

2014-10-01

... infectious blood and blood components—(1) Potentially human immunodeficiency virus (HIV) infectious blood and blood components. Potentially HIV infectious blood and blood components are prior collections from a donor— (i) Who tested negative at the time of donation but tests reactive for evidence of HIV infection...

42 CFR 482.27 - Condition of participation: Laboratory services.

Code of Federal Regulations, 2011 CFR

2011-10-01

... infectious blood and blood components—(1) Potentially human immunodeficiency virus (HIV) infectious blood and blood components. Potentially HIV infectious blood and blood components are prior collections from a donor— (i) Who tested negative at the time of donation but tests reactive for evidence of HIV infection...

Transcriptomic Analysis of the Effects of a Fish Oil Enriched Diet on Murine Brains

DTIC Science & Technology

2014-03-14

concerns associated with psychological bias due to the handling with variable frequency [43]. Possible bias due to the rodents’ potential favoring of... tested herein. Discussion A multitude of in vitro results suggests potential benefits of n-3 PUFA enriched diets typically supplemented by fish oil, but...101–103]. 4.3 Potential therapeutic efficacy of FD treating neurodegenarative disorders The motivation of testing fish oil as the dietary

Understanding the medical and nonmedical value of diagnostic testing.

PubMed

Lee, David W; Neumann, Peter J; Rizzo, John A

2010-01-01

To develop a framework for defining the potential value of diagnostic testing, and discuss its implications for the health-care delivery system. We reviewed the conceptual and empirical literature related to the valuing of diagnostic tests, and used this information to create a framework for characterizing their value. We then made inferences about the impact of this framework on health insurance coverage, health technology assessment, physician-patient relationships, and public health policy. Three dimensions can effectively classify the potential value created by diagnostic tests: 1) medical value (impact on treatment decisions); 2) planning value (affect on patients' ability to make better life decisions); and 3) psychic value (how test information affects patients' sense of self). This comprehensive framework for valuing diagnostics suggests that existing health technology assessments may systematically under- or overvalue diagnostics, leading to potentially incorrect conclusions about cost-effectiveness. Further, failure to account for all value dimensions may lead to distorted payments under a value-based health-care system. The potential value created by medical diagnostics incorporates medical value as well as value associated with well-being and planning. Consideration of all three dimensions has important implications for technology assessment and value-based payment.

Charge movement in a fast twitch skeletal muscle from rat.

PubMed

Simon, B J; Beam, K G

1983-02-01

Voltage-dependent charge movement in the rat omohyoid muscle was investigated using the three microelectrode voltage clamp technique. The charge that moved during a depolarization from the holding potential (-90 mV) to the test potential, V, increased with increasing V, saturating around 0 mV. The charge vs. voltage relationship was well fitted by Q = Q(max)/{1 + exp[-(V - V)/k]}, with Q(max) = 28.5 nC/muF, V = -34.2 mV, and k = 8.7 mV. Repolarization of the fiber from the test potential back to the holding potential caused an equal but opposite amount of charge to move. The kinetics of ON charge movement could be well described by a model developed for frog muscle by Horowicz and Schneider (1981b), which suggests that rat and frog charge movements are similar. This model failed to describe the kinetics of OFF charge movement for steps in potential from 0 mV to test potentials of -10 to -90 mV. OFF-charge movement rose to a peak more slowly and decayed more slowly than predicted by the theory.

Initial Plasma Testing of the Ion Proportional Surface Emission Cathode

DTIC Science & Technology

2008-07-15

REPRINT 3. DATES COVERED (From - To) 4. TITLE AND SUBTITLE Initial Plasma Testing of the Ion Proportional Surface Emission Cathode 5a. CONTRACT NUMBER...substrate and an adjacent metal cathode element. The substrate potential is held positive of the cathode with gate elements. In plasma , the gate is...eliminated due to ambient ion flux which maintains the substrate potential near plasma ground. Prototype devices have been tested using a laboratory plasma

F-35A Training Basing Environmental Impact Statement. Volume 1

DTIC Science & Technology

2012-06-01

Global Change Research Program USMC U.S. Marine Corps USN U.S. Navy UTTR Utah Test and Training Range VCP vitrified clay pipe VFR Visual Flight...burning flare struck the ground, it could result in a fire, with potential environmental consequences. The design , manufacturing, and testing process...C–6, and C–7). Of these, 14 are considered to have the potential to be designated as an NRHP Missile Test Stands Historic District. Premilitary

Economic evaluations of point of care testing strategies for active tuberculosis.

PubMed

Zwerling, Alice; Dowdy, David

2013-06-01

Point of care (POC) diagnostics are often hailed as having the potential to transform tuberculosis (TB) control efforts. However, POC testing is better conceptualized as a system of diagnosis and treatment, not simply a test that can provide rapid, deployable results. Economic evaluations may help decision makers allocate scarce resources for TB control, but evaluations of POC testing face unique challenges that include evaluating the full diagnostic system, incorporating implementation costs, translating diagnostic results into health and accounting for downstream treatment costs. For economic evaluations to reach their full potential as decision-making tools for POC testing in TB, these challenges must be understood and addressed.

PNTAB view : minimum criteria for testing/evaluation of interference potential of high power terrestrial transmitters in repurposed radio bands.

DOT National Transportation Integrated Search

2017-03-30

Brief, 6-point set of guidelines that describe how to test the interference potential of high power terrestrial transmitters in repurposed radio bands. Presented at Global Positioning System Adjacent Band Compatibility Assessment Workshop VI, 03/30/2...

Occupational Potential in a Population with Duchenne Muscular Dystrophy.

ERIC Educational Resources Information Center

Schkade, Janette K.; And Others

1987-01-01

Twenty-five males with Duchenne muscular dystrophy were tested to assess their potential for occupational activity. Tests measured possible sensory deficits, strength, endurance, and fatigue in response to sustained fine motor activity. Results indicate that, within limitations, persons with this diagnosis can engage in activity leading to skill…

76 FR 49473 - Petition to Maximize Practical Utility of List 1 Chemicals Screened Through EPA's Endocrine...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-08-10

... Utility of List 1 Chemicals Screened Through EPA's Endocrine Disruptor Screening Program; Notice of... to the test orders issued under the Endocrine Disruptor Screening Program. DATES: Comments must be... testing of chemical substances for potential endocrine effects. Potentially affected entities, identified...

Mutagenic Potential of Nitroguanidine in the Drosophila melanogaster Sex-Linked Recessive Lethal Test

DTIC Science & Technology

1988-07-01

Security Classification) Mtutagenic potential of nitroguan idine in the Drosophila melano- gaster sex-linked recessive lethal test 12. PERSONAL AUTHOR(S...Frederick, MD 21701-5012 Commander Commandant US Army Environmental Hygine Academy of Health Sciences. US Army Agency ATTN: AHS-CDM ATTN: Librarian, HSDH

16 CFR 1505.6 - Performance.

Code of Federal Regulations, 2010 CFR

2010-01-01

... horizontal. No spillage of molten material or hot liquids from containers shall occur while the toy is... breakdown for 1 minute a sinusoidal test potential applied between the high-voltage and low-voltage windings... volts plus twice the rated voltage of the high-voltage winding. The test potential shall be supplied...

MYSID CRUSTACEANS AS POTENTIAL TEST ORGANISMS FOR THE EVALUATION OF ENVIRONMENTAL ENDOCRINE DISRUPTORS: A REVIEW

EPA Science Inventory

Verslycke, Tim A., Nancy Fockedey, Charles L. McKenney, Jr., Stephen D. Roast, Malcolm B. Jones, Jan Mees and Colin R. Janssen. 2004. Mysid Crustaceans as Potential Test Organisms for the Evaluation of Environmental Endocrine Disruption: A Review. Environ. Toxicol. Chem. 23(5):12...

The MIMIC Model as a Tool for Differential Bundle Functioning Detection

ERIC Educational Resources Information Center

Finch, W. Holmes

2012-01-01

Increasingly, researchers interested in identifying potentially biased test items are encouraged to use a confirmatory, rather than exploratory, approach. One such method for confirmatory testing is rooted in differential bundle functioning (DBF), where hypotheses regarding potential differential item functioning (DIF) for sets of items (bundles)…

20170921 - An evaluation of selected (Q)SARs/expert systems for the Prediction of Skin Sensitization Potential (ASCCT)

EPA Science Inventory

Predictive testing to characterize substances for their skin sensitization potential has historically been based on animal models such as the Local Lymph Node Assay (LLNA) and the Guinea Pig Maximization Test (GPMT). In recent years, EU regulations have provided a strong incentiv...

Predictive Endocrine Testing in the 21st Century Using In Vitro Assays of Estrogen Receptor Signaling Responses

EPA Science Inventory

Thousands of environmental chemicals are subject to regulatory review for their potential to be endocrine disruptors (ED). In vitro high-throughput screening (HTS) assays have emerged as a potential tool for prioritizing chemicals for ED-related whole-animal tests. In this study,...

F-18 FDG PET, CT, and MRI for detecting the malignant potential in patients with gastrointestinal stromal tumors: A protocol for a network meta-analysis of diagnostic test accuracy.

PubMed

Wei, Kongyuan; Pan, Bei; Yang, Huan; Lu, Cuncun; Ge, Long; Cao, Nong

2018-04-01

Gastrointestinal stromal tumor (GIST) is a rare cancer in gastrointestinal carcinomas and has been widely known as a curable disease among all the digestive tumors. However, early detection of malignant potential in patients with GIST has still been a huge challenge all around the world. CT, MRI, and F-18 FDG PET are all considered as good tests for diagnosing malignant GIST efficiently, but no recommended suggestions presents which test among the 3 is the prior one in detecting the malignant potential of GIST. We perform this study to assess the accuracy between CT, MRI, and F-18 FDG PET through network meta-analysis method, and to rank these tests. PubMed, EMBASE.com, CNKI, and CBM databases will be searched without search date and language restrictions. We will include diagnostic tests which assessed the accuracy of CT, MRI, and F-18 FDG PET in detecting the malignant potential of GIST. The risk of bias in each study will be independently assessed as low, moderate, or high using criteria adapted from Quality Assessment of Diagnostic Accuracy Studies 2 (QUADAS-2). Meta-analysis will be performed using STATA 12.0 and R 3.4.1 software. The competing diagnostic tests will be ranked by a superiority index. This study is ongoing, and will be submitted to a peer-reviewed journal for publication. This study will provide a comprehensive evidence summary of CT, MRI, and F-18 FDG PET in detecting the malignant potential of GIST.

Skin sensitisation: the Colipa strategy for developing and evaluating non-animal test methods for risk assessment.

PubMed

Maxwell, Gavin; Aeby, Pierre; Ashikaga, Takao; Bessou-Touya, Sandrine; Diembeck, Walter; Gerberick, Frank; Kern, Petra; Marrec-Fairley, Monique; Ovigne, Jean-Marc; Sakaguchi, Hitoshi; Schroeder, Klaus; Tailhardat, Magali; Teissier, Silvia; Winkler, Petra

2011-01-01

Allergic contact dermatitis is a delayed-type hypersensitivity reaction induced by small reactive chemicals (haptens). Currently, the sensitising potential and potency of new chemicals is usually characterised using data generated via animal studies, such as the local lymph node assay (LLNA). There are, however, increasing public and political concerns regarding the use of animals for the testing of new chemicals. Consequently, the development of in vitro, in chemico or in silico models for predicting the sensitising potential and/or potency of new chemicals is receiving widespread interest. The Colipa Skin Tolerance task force currently collaborates with and/or funds several academic research groups to expand our understanding of the molecular and cellular events occurring during the acquisition of skin sensitisation. Knowledge gained from this research is being used to support the development and evaluation of novel alternative approaches for the identification and characterisation of skin sensitizing chemicals. At present three non-animal test methods (Direct Peptide Reactivity Assay (DPRA), Myeloid U937 Skin Sensitisation Test (MUSST) and human Cell Line Activation Test (hCLAT)) have been evaluated in Colipa interlaboratory ring trials for their potential to predict skin sensitisation potential and were recently submitted to ECVAM for formal pre-validation. Data from all three test methods will now be used to support the study and development of testing strategy approaches for skin sensitiser potency prediction. This publication represents the current viewpoint of the cosmetics industry on the feasibility of replacing the need for animal test data for informing skin sensitisation risk assessment decisions.

Oxygen Compatibility Testing of Composite Materials

NASA Technical Reports Server (NTRS)

Engel, Carl D.; Watkins, Casey N.

2006-01-01

Composite materials offer significant weight-saving potential for aerospace applications in propellant and oxidizer tanks. This application for oxygen tanks presents the challenge of being oxygen compatible in addition to complying with the other required material characteristics. This effort reports on the testing procedures and data obtained in examining and selecting potential composite materials for oxygen tank usage. Impact testing of composites has shown that most of these materials initiate a combustion event when impacted at 72 ft-lbf in the presence of liquid oxygen, though testing has also shown substantial variability in reaction sensitivities to impact. Data for screening of 14 potential composites using the Bruceton method is given herein and shows that the 50-percent reaction frequencies range from 17 to 67 ft-lbf. The pressure and temperature rises for several composite materials were recorded to compare the energy releases as functions of the combustion reactions with their respective reaction probabilities. The test data presented are primarily for a test pressure of 300 psia in liquid oxygen. The impact screening process is compared with oxygen index and autogenous ignition test data for both the composite and the basic resin. The usefulness of these supplemental tests in helping select the most oxygen compatible materials is explored. The propensity for mechanical impact ignition of the composite compared with the resin alone is also examined. Since an ignition-free composite material at the peak impact energy of 72 ft-lbf has not been identified, composite reactivity must be characterized over the impact energy level and operating pressure ranges to provide data for hazard analyses in selecting the best potential material for liquid tank usage.

The Noninvasive Measurement of X-Ray Tube Potential.

NASA Astrophysics Data System (ADS)

Ranallo, Frank Nunzio

In this thesis I briefly describe the design of clinical x-ray imaging systems and also the various methods of measuring x-ray tube potential, both invasive and noninvasive. I also discuss the meaning and usage of the quantities tube potential (kV) and peak tube potential (kVp) with reference to x-ray systems used in medical imaging. I propose that there exist several quantities which describe different important aspects of the tube potential as a function of time. These quantities are measurable and can be well defined. I have developed a list of definitions of these quantities along with suggested names and symbols. I describe the development and physical principles of a superior noninvasive method of tube potential measurement along with the instrumentation used to implement this method. This thesis research resulted in the development of several commercial kVp test devices (or "kVp Meters") for which the actual measurement procedure is simple, rapid, and reliable compared to other methods, invasive or noninvasive. These kVp test devices provide measurements with a high level of accuracy and reliability over a wide range of test conditions. They provide results which are more reliable and clinically meaningful than many other, more primary and invasive methods. The errors inherent in these new kVp test devices were investigated and methods to minimize them are discussed.

Revisiting the Rossby Haurwitz wave test case with contour advection

NASA Astrophysics Data System (ADS)

Smith, Robert K.; Dritschel, David G.

2006-09-01

This paper re-examines a basic test case used for spherical shallow-water numerical models, and underscores the need for accurate, high resolution models of atmospheric and ocean dynamics. The Rossby-Haurwitz test case, first proposed by Williamson et al. [D.L. Williamson, J.B. Drake, J.J. Hack, R. Jakob, P.N. Swarztrauber, A standard test set for numerical approximations to the shallow-water equations on the sphere, J. Comput. Phys. (1992) 221-224], has been examined using a wide variety of shallow-water models in previous papers. Here, two contour-advective semi-Lagrangian (CASL) models are considered, and results are compared with previous test results. We go further by modifying this test case in a simple way to initiate a rapid breakdown of the basic wave state. This breakdown is accompanied by the formation of sharp potential vorticity gradients (fronts), placing far greater demands on the numerics than the original test case does. We also go further by examining other dynamical fields besides the height and potential vorticity, to assess how well the models deal with gravity waves. Such waves are sensitive to the presence or not of sharp potential vorticity gradients, as well as to numerical parameter settings. In particular, large time steps (convenient for semi-Lagrangian schemes) can seriously affect gravity waves but can also have an adverse impact on the primary fields of height and velocity. These problems are exacerbated by a poor resolution of potential vorticity gradients.

Synthesis of Sine-on-Random vibration profiles for accelerated life tests based on fatigue damage spectrum equivalence

NASA Astrophysics Data System (ADS)

Angeli, Andrea; Cornelis, Bram; Troncossi, Marco

2018-03-01

In many real life environments, mechanical and electronic systems are subjected to vibrations that may induce dynamic loads and potentially lead to an early failure due to fatigue damage. Thus, qualification tests by means of shakers are advisable for the most critical components in order to verify their durability throughout the entire life cycle. Nowadays the trend is to tailor the qualification tests according to the specific application of the tested component, considering the measured field data as reference to set up the experimental campaign, for example through the so called "Mission Synthesis" methodology. One of the main issues is to define the excitation profiles for the tests, that must have, besides the (potentially scaled) frequency content, also the same damage potential of the field data despite being applied for a limited duration. With this target, the current procedures generally provide the test profile as a stationary random vibration specified by a Power Spectral Density (PSD). In certain applications this output may prove inadequate to represent the nature of the reference signal, and the procedure could result in an unrealistic qualification test. For instance when a rotating part is present in the system the component under analysis may be subjected to Sine-on-Random (SoR) vibrations, namely excitations composed of sinusoidal contributions superimposed to random vibrations. In this case, the synthesized test profile should preserve not only the induced fatigue damage but also the deterministic components of the environmental vibration. In this work, the potential advantages of a novel procedure to synthesize SoR profiles instead of PSDs for qualification tests are presented and supported by the results of an experimental campaign.

National trends in safety performance of electronic health record systems in children's hospitals.

PubMed

Chaparro, Juan D; Classen, David C; Danforth, Melissa; Stockwell, David C; Longhurst, Christopher A

2017-03-01

To evaluate the safety of computerized physician order entry (CPOE) and associated clinical decision support (CDS) systems in electronic health record (EHR) systems at pediatric inpatient facilities in the US using the Leapfrog Group's pediatric CPOE evaluation tool. The Leapfrog pediatric CPOE evaluation tool, a previously validated tool to assess the ability of a CPOE system to identify orders that could potentially lead to patient harm, was used to evaluate 41 pediatric hospitals over a 2-year period. Evaluation of the last available test for each institution was performed, assessing performance overall as well as by decision support category (eg, drug-drug, dosing limits). Longitudinal analysis of test performance was also carried out to assess the impact of testing and the overall trend of CPOE performance in pediatric hospitals. Pediatric CPOE systems were able to identify 62% of potential medication errors in the test scenarios, but ranged widely from 23-91% in the institutions tested. The highest scoring categories included drug-allergy interactions, dosing limits (both daily and cumulative), and inappropriate routes of administration. We found that hospitals with longer periods since their CPOE implementation did not have better scores upon initial testing, but after initial testing there was a consistent improvement in testing scores of 4 percentage points per year. Pediatric computerized physician order entry (CPOE) systems on average are able to intercept a majority of potential medication errors, but vary widely among implementations. Prospective and repeated testing using the Leapfrog Group's evaluation tool is associated with improved ability to intercept potential medication errors. © The Author 2016. Published by Oxford University Press on behalf of the American Medical Informatics Association. All rights reserved. For Permissions, please email: journals.permissions@oup.com

Evaluating the sensitization potential of surfactants: integrating data from the local lymph node assay, guinea pig maximization test, and in vitro methods in a weight-of-evidence approach.

PubMed

Ball, Nicholas; Cagen, Stuart; Carrillo, Juan-Carlos; Certa, Hans; Eigler, Dorothea; Emter, Roger; Faulhammer, Frank; Garcia, Christine; Graham, Cynthia; Haux, Carl; Kolle, Susanne N; Kreiling, Reinhard; Natsch, Andreas; Mehling, Annette

2011-08-01

An integral part of hazard and safety assessments is the estimation of a chemical's potential to cause skin sensitization. Currently, only animal tests (OECD 406 and 429) are accepted in a regulatory context. Nonanimal test methods are being developed and formally validated. In order to gain more insight into the responses induced by eight exemplary surfactants, a battery of in vivo and in vitro tests were conducted using the same batch of chemicals. In general, the surfactants were negative in the GPMT, KeratinoSens and hCLAT assays and none formed covalent adducts with test peptides. In contrast, all but one was positive in the LLNA. Most were rated as being irritants by the EpiSkin assay with the additional endpoint, IL1-alpha. The weight of evidence based on this comprehensive testing indicates that, with one exception, they are non-sensitizing skin irritants, confirming that the LLNA tends to overestimate the sensitization potential of surfactants. As results obtained from LLNAs are considered as the gold standard for the development of new nonanimal alternative test methods, results such as these highlight the necessity to carefully evaluate the applicability domains of test methods in order to develop reliable nonanimal alternative testing strategies for sensitization testing. Copyright © 2011 Elsevier Inc. All rights reserved.

Personal Narratives of Genetic Testing: Expectations, Emotions, and Impact on Self and Family.

PubMed

Anderson, Emily E; Wasson, Katherine

2015-01-01

The stories in this volume shed light on the potential of narrative inquiry to fill gaps in knowledge, particularly given the mixed results of quantitative research on patient views of and experiences with genetic and genomic testing. Published studies investigate predictors of testing (particularly risk perceptions and worry); psychological and behavioral responses to testing; and potential impact on the health care system (e.g., when patients bring DTC genetic test results to their primary care provider). Interestingly, these themes did not dominate the narratives published in this issue. Rather, these narratives included consistent themes of expectations and looking for answers; complex emotions; areas of contradiction and conflict; and family impact. More narrative research on patient experiences with genetic testing may fill gaps in knowledge regarding how patients define the benefits of testing, changes in psychological and emotional reactions to test results over time, and the impact of testing on families.

40 CFR 86.1846-01 - Manufacturer in-use confirmatory testing requirements.

Code of Federal Regulations, 2014 CFR

2014-07-01

... under this section applies separately to each test group and at each test point (low and high mileage... with only one test group under § 86.1845, such manufacturer shall have a maximum potential testing... confirmatory testing requirements. (a) General requirements. (1) Manufacturers must test, or cause testing to...

Impact Testing of Composites for Aircraft Engine Fan Cases

NASA Technical Reports Server (NTRS)

Roberts, Gary D.; Revilock, Duane M.; Binienda, Wieslaw K.; Nie, Walter Z.; Mackenzie, S. Ben; Todd, Kevin B.

2001-01-01

Before composite materials can be considered for use in the fan case of a commercial jet engine, the performance of a composite structure under blade-out loads needs to be demonstrated. The objective of this program is to develop an efficient test and analysis method for evaluating potential composite case concepts. Ballistic impact tests were performed on laminated glass/epoxy composites in order to identify potential failure modes and to provide data for analysis. Flat 7x7 in. panels were impacted with cylindrical titanium projectiles, and 15 in. diameter half-rings were impacted with wedge-shaped titanium projectiles. Composite failure involved local fiber fracture as well as tearing and delamination on a larger scale. A 36 in. diameter full-ring subcomponent was proposed for larger scale testing. Explicit, transient, finite element analyses were used to evaluate impact dynamics and subsequent global deformation for the proposed full-ring subcomponent test. Analyses on half-ring and quarter ring configurations indicated that less expensive smaller scale tests could be used to screen potential composite concepts when evaluation of local impact damage is the primary concern.

Novel design strategy for checkpoint kinase 2 inhibitors using pharmacophore modeling, combinatorial fusion, and virtual screening.

PubMed

Lin, Chun-Yuan; Wang, Yen-Ling

2014-01-01

Checkpoint kinase 2 (Chk2) has a great effect on DNA-damage and plays an important role in response to DNA double-strand breaks and related lesions. In this study, we will concentrate on Chk2 and the purpose is to find the potential inhibitors by the pharmacophore hypotheses (PhModels), combinatorial fusion, and virtual screening techniques. Applying combinatorial fusion into PhModels and virtual screening techniques is a novel design strategy for drug design. We used combinatorial fusion to analyze the prediction results and then obtained the best correlation coefficient of the testing set (r test) with the value 0.816 by combining the Best(train)Best(test) and Fast(train)Fast(test) prediction results. The potential inhibitors were selected from NCI database by screening according to Best(train)Best(test) + Fast(train)Fast(test) prediction results and molecular docking with CDOCKER docking program. Finally, the selected compounds have high interaction energy between a ligand and a receptor. Through these approaches, 23 potential inhibitors for Chk2 are retrieved for further study.

Potential of Organic Matrix Composites for Liquid Oxygen Tank

NASA Technical Reports Server (NTRS)

Davis, Samuel E.; Herald, Stephen D.; Stolzfus, Joel M.; Engel, Carl D.; Bohlen, James W.; Palm, Tod; Robinson, Michael J.

2005-01-01

Composite materials are being considered for the tankage of cryogenic propellants in access to space because of potentially lower structural weights. A major hurdle for composites is an inherent concern about the safety of using flammable structural materials in contact with liquid and gaseous oxygen. A hazards analysis approach addresses a series of specific concerns that must be addressed based upon test data. Under the 2nd Generation Reusable Launch Vehicle contracts, testing was begun for a variety of organic matrix composite materials both to aid in the selection of materials and to provide needed test data to support hazards analyses. The work has continued at NASA MSFC and the NASA WSTF to provide information on the potential for using composite materials in oxygen systems. Appropriate methods for oxygen compatibility testing of structural materials and data for a range of composite materials from impact, friction, flammability and electrostatic discharge testing are presented. Remaining concerns and conclusions about composite tank structures, and recommendations for additional testing are discussed. Requirements for system specific hazards analysis are identified.

The mammalian spot test and its use for the testing of potential carcinogenicity of welding fume particles and hexavalent chromium.

PubMed

Knudsen, I

1980-07-01

Welding fume particles, potassium chromate and cyclophosphamide are tested in the mammalian spot test. Female mice C57BL/6J/BOM9 weeks old have been mated to T-stock male mice and treated with welding fume particles 100 mg/kg, potassium chromate 20 or 10 mg/kg, or cyclophosphamide 10 or 2.5 mg/kg intraperitoneally at day 8, 9 and 10 of pregnancy. The fur of the offspring was checked week 2 through week 5 after birth for coloured spots. The characterisation of the different types of spots are discussed. Welding fume particles 100 mg/kg and potassium chromate 10 mg/kg induce approximately to the same extent as cyclophosphamde 2.5 mg/kg, grayish or brownish spots in tvo screening test for mutagenic and carcinogenic potential of chemicals. The positive results for potassium chromate and cyclophosphamide are in agreement with previous in vitro experiments and confirm the sensitivity of the test. The effect of welding fume particles in this in vivo system suggests a potential risk for humans directly exposed to welding fumes.

Bend it like Beckham! The Ethics of Genetically Testing Children for Athletic Potential

PubMed Central

Camporesi, Silvia

2016-01-01

The recent boom of direct-to-consumer (DTC) genetic tests, aimed at measuring children’s athletic potential, is the latest wave in the ‘pre-professionalization’ of children that has characterized, especially but not exclusively, the USA in the last 15 years or so. In this paper, I analyse the use of DTC genetic tests, sometimes coupled with more traditional methods of ‘talent scouting’, to assess a child’s predisposition to athletic performance. I first discuss the scientific evidence at the basis of these tests, and the parental decision in terms of education, and of investing in the children’s future, taken on the basis of the results of the tests. I then discuss how these parental practices impact on the children’s right to an open future, and on their developing sense of autonomy. I also consider the meaning and role of sports in childhood, and conclude that the use of DTC genetic tests to measure children’s athletic potential should be seen as a ‘wake up’ call for other problematic parental attitudes aimed at scouting and developing children’s talent. PMID:27996058

Rapid HIV Testing in Dental Practices

PubMed Central

Abel, Stephen N.; Pereyra, Margaret; Liguori, Terri; Pollack, Harold A.; Metsch, Lisa R.

2012-01-01

Despite increasing discussion about the dental care setting as a logical, potentially fruitful venue for rapid HIV testing, dentists’ willingness to take on this task is unclear. Semistructured interviews with 40 private practice dentists revealed their principal concerns regarding offering patients HIV testing were false results, offending patients, viewing HIV testing as outside the scope of licensure, anticipating low patient acceptance of HIV testing in a dental setting, expecting inadequate reimbursement, and potential negative impact on the practice. Dentists were typically not concerned about transmission risks, staff opposition to testing, or making referrals for follow-up after a positive result. A larger cultural change may be required to engage dentists more actively in primary prevention and population-based HIV screening. PMID:22397342

Progress toward determining the potential of ODS alloys for gas turbine applications

NASA Technical Reports Server (NTRS)

Dreshfield, R. L.; Hoppin, G., III; Sheffler, K.

1983-01-01

The Materials for Advanced Turbine Engine (MATE) Program managed by the NASA Lewis Research Center is supporting two projects to evaluate the potential of oxide dispersion strengthened (ODS) alloys for aircraft gas turbine applications. One project involves the evaluation of Incoloy (TM) MA-956 for application as a combustor liner material. An assessment of advanced engine potential will be conducted by means of a test in a P&WA 2037 turbofan engine. The other project involves the evaluation of Inconel (TM) MA 6000 for application as a high pressure turbine blade material and includes a test in a Garrett TFE 731 turbofan engine. Both projects are progressing toward these engine tests in 1984.

Acceptable Interventions to Reduce Syphilis Transmission Among High-Risk Men Who Have Sex With Men in Los Angeles

PubMed Central

Plant, Aaron; Javanbakht, Marjan; Cross, John; Montoya, Jorge A.; Bolan, Robert; Kerndt, Peter R.

2015-01-01

Objectives. We examined perceptions of and attitudes toward existing and potential syphilis interventions, including case management and Web-based programs, to increase syphilis testing among high-risk men who have sex with men (MSM). Methods. Between October 2010 and June 2011, we conducted in-depth interviews with 19 MSM in Los Angeles, California, with repeat early syphilis infections (primary, secondary, and early latent syphilis) within the previous 5 years. We analyzed the interviews inductively to determine the most acceptable potential interventions. Results. Experiences with health department and community-based standard of care case management were generally positive. The most popular interventions among respondents included a Web site providing information on syphilis and syphilis testing, automated Web reminders to test, being paid to test, free online home testing kits, and preexposure prophylactic medication. Respondents’ beliefs that they would continue to practice high-risk sexual behaviors reinforced their reasons for wanting increased accessibility and convenient testing strategies. Conclusions. Public health officials should consider participant responses to potential interventions for syphilis, which suggest that high-risk MSM would consider testing more often or using other interventions. PMID:25602881

Multiple Changes to Reusable Solid Rocket Motors, Identifying Hidden Risks

NASA Technical Reports Server (NTRS)

Greenhalgh, Phillip O.; McCann, Bradley Q.

2003-01-01

The Space Shuttle Reusable Solid Rocket Motor (RSRM) baseline is subject to various changes. Changes are necessary due to safety and quality improvements, environmental considerations, vendor changes, obsolescence issues, etc. The RSRM program has a goal to test changes on full-scale static test motors prior to flight due to the unique RSRM operating environment. Each static test motor incorporates several significant changes and numerous minor changes. Flight motors often implement multiple changes simultaneously. While each change is individually verified and assessed, the potential for changes to interact constitutes additional hidden risk. Mitigating this risk depends upon identification of potential interactions. Therefore, the ATK Thiokol Propulsion System Safety organization initiated the use of a risk interaction matrix to identify potential interactions that compound risk. Identifying risk interactions supports flight and test motor decisions. Uncovering hidden risks of a full-scale static test motor gives a broader perspective of the changes being tested. This broader perspective compels the program to focus on solutions for implementing RSRM changes with minimal/mitigated risk. This paper discusses use of a change risk interaction matrix to identify test challenges and uncover hidden risks to the RSRM program.

Cinnamic aldehyde: a survey of consumer patch-test sensitization.

PubMed

Danneman, P J; Booman, K A; Dorsky, J; Kohrman, K A; Rothenstein, A S; Sedlak, R I; Steltenkamp, R J; Thompson, G R

1983-12-01

The potential for cinnamic aldehyde, an important fragrance and flavour ingredient, to induce or to elicit delayed contact hypersensitivity reactions in man was evaluated by analysing patch-test data. Results of studies involving a total of 4117 patch tests on various consumer products and fragrance blends containing cinnamic aldehyde and on the material itself were collected from fragrance and formulator companies. The data indicate that cinnamic aldehyde contained in consumer products and fragrance blends at concentrations up to 6 X 10(-1)%, and patch-tested at concentrations up to 8 X 10(-3)%, has no detectable potential to induce hypersensitivity. Cinnamic aldehyde when tested alone induced a dose-related hypersensitivity response. According to published reports, cinnamic aldehyde elicited positive delayed hypersensitivity responses in dermatitic patients. However, results of the current survey show that when cinnamic aldehyde was tested alone or as part of a mixture in subjects in the general population, no pre-existing hypersensitivity reactions to the fragrance material were observed in any of the 4117 patch tests which constituted the survey. Cinnamic aldehyde at the concentrations contained in consumer products and fragrances, has a very low potential to induce hypersensitivity ('induced' reactions) or to elicit sensitization reactions ('elicited' reactions) in the general population.

Effect of electrochemical redox reaction on growth and metabolism of Saccharomyces cerevisiae as an environmental factor.

PubMed

Na, Kwan Byung; Hwang, Tae Sik; Lee, Sung Hun; Ahn, Dae Hee; Park, Doo Hyun

2007-03-01

The effect of an electrochemically generated oxidation-reduction potential and electric pulse on ethanol production and growth of Saccharomyces cerevisiae ATCC 26603 was experimented and compared with effects of electron mediators (neutral red, benzyl viologen, and thionine), chemical oxidants (hydrogen peroxide and hypochlorite), chemical reductants (sulfite and nitrite), oxygen, and hydrogen. The oxidation (anodic) and reduction (cathodic) potential and electric pulse activated ethanol production and growth, and changed the total soluble protein pattern of the test strain. Neutral red electrochemically reduced activated ethanol production and growth of the test strain, but benzyl viologen and thionine did not. Nitrite inhibited ethanol production but did not influence growth of the test strain. Hydrogen peroxide, hypochlorite, and sulfite did not influence ethanol production and growth of the test strain. Hydrogen and oxygen also did not influence the growth and ethanol production. It shows that the test strain may perceive electrochemically generated oxidation-reduction potential and electric pulse as an environmental factor.

Informed choice in direct-to-consumer genetic testing (DTCGT) websites: a content analysis of benefits, risks, and limitations

PubMed Central

Singleton, Amanda; Erby, Lori Hamby; Foisie, Kathryn V.; Kaphingst, Kimberly

2012-01-01

An informed choice about health-related direct-to-consumer genetic testing (DTCGT) requires knowledge of potential benefits, risks, and limitations. To understand the information that potential consumers of DTCGT services are exposed to on company websites, we conducted a content analysis of 23 health-related DTCGT websites. Results revealed that benefit statements outweighed risk and limitation statements 6 to 1. The most frequently described benefits were 1) disease prevention, 2) consumer education, 3) personalized medical recommendations, and 4) the ability to make health decisions. Thirty-five percent of websites also presented at least one risk of testing. Seventy-eight percent of websites mentioned at least one limitation of testing. Based on this information, potential consumers might get an inaccurate picture of genetic testing which could impact their ability to make an informed decision. Practices that enhance the presentation of balanced information on DTCGT company websites should be encouraged. PMID:22194036

The anaerobic potentially mineralizable nitrogen test as a tool for nitrogen management in the Midwest

USDA-ARS?s Scientific Manuscript database

The anaerobic potentially mineralizable nitrogen (PMNan) test is a tool that can improve estimations of mineralizable nitrogen (N) and enhance nitrogen use efficiency. This tool may also help improve predictions of N uptake, grain yield, and the economic optimum nitrogen rate (EONR) of corn (Zea ma...

IATA for skin sensitization potential – 1 out of 2 or 2 out of 3? (ESCD meeting)

EPA Science Inventory

To meet EU regulatory requirements and to avoid or minimize animal testing, there is a need for non-animal methods to assess skin sensitization potential. Given the complexity of the skin sensitization endpoint, there is an expectation that integrated testing and assessment appro...

IATA for skin sensitization potential – 1 out of 2 or 2 out of 3? (ASCCT meeting)

EPA Science Inventory

To meet EU regulatory requirements and to avoid or minimize animal testing, there is a need for non-animal methods to assess skin sensitization potential. Given the complexity of the skin sensitization endpoint, there is an expectation that integrated testing and assessment appro...

76 FR 80905 - TRICARE Evaluation of Centers for Medicare & Medicaid Services Approved Laboratory Developed...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-12-27

... potential high utilization and potential high clinical impact on TRICARE beneficiaries. If no submission is... reviewed in numerical order beginning with the test listed as having the highest priority. Those selected... laboratories that use LDTs as well as FDA approved tests. Laboratories performing moderate or high complexity...

MSU-Test: A Tool for Measuring Students' Achievement

ERIC Educational Resources Information Center

Chansirisira, Pacharawit; Nuangchalerm, Prasart; Morakot, Nongnit; Khamkong, Surasak

2011-01-01

The study aims to employ MSU-test as a tool to measure Mahasarakham student in secondary and high school levels to achieve their learning potential. The importance of this study will help university understanding school potential and provide information to increase students' score. Two thousand and seven hundred eight nine students participated in…

Tests of potential functional barriers for laminated multilayer food packages. Part I: Low molecular weight permeants.

PubMed

Simal-Gándara, J; Sarria-Vidal, M; Koorevaar, A; Rijk, R

2000-08-01

The advent of the functional barrier concept in food packaging has brought with it a requirement for fast tests of permeation through potential barrier materials. In such tests it would be convenient for both foodstuffs and materials below the functional barrier (sub-barrier materials) to be represented by standard simulants. By means of inverse gas chromatography, liquid paraffin spiked with appropriate permeants was considered as a potential simulant of sub-barrier materials based on polypropylene (PP) or similar polyolefins. Experiments were performed to characterize the kinetics of the permeation of low molecular weight model permeants (octene, toluene and isopropanol) from liquid paraffin, through a surrogate potential functional barrier (25 microns-thick oriented PP) into the food stimulants olive oil and 3% (w/v) acetic acid. These permeation results were interpreted in terms of three permeation kinetic models regarding the solubility of a particular model permeant in the post-barrier medium (i.e. the food simulant). The results obtained justify the development and evaluation of liquid sub-barrier simulants that would allow flexible yet rigorous testing of new laminated multilayer packaging materials.

TRANSIT TIMING OBSERVATIONS FROM KEPLER. VI. POTENTIALLY INTERESTING CANDIDATE SYSTEMS FROM FOURIER-BASED STATISTICAL TESTS

DOE Office of Scientific and Technical Information (OSTI.GOV)

Steffen, Jason H.; Ford, Eric B.; Rowe, Jason F.

2012-09-10

We analyze the deviations of transit times from a linear ephemeris for the Kepler Objects of Interest (KOI) through quarter six of science data. We conduct two statistical tests for all KOIs and a related statistical test for all pairs of KOIs in multi-transiting systems. These tests identify several systems which show potentially interesting transit timing variations (TTVs). Strong TTV systems have been valuable for the confirmation of planets and their mass measurements. Many of the systems identified in this study should prove fruitful for detailed TTV studies.

Transit Timing Observations from Kepler: VII. Potentially interesting candidate systems from Fourier-based statistical tests

DOE Office of Scientific and Technical Information (OSTI.GOV)

Steffen, Jason H.; /Fermilab; Ford, Eric B.

2012-01-01

We analyze the deviations of transit times from a linear ephemeris for the Kepler Objects of Interest (KOI) through Quarter six (Q6) of science data. We conduct two statistical tests for all KOIs and a related statistical test for all pairs of KOIs in multi-transiting systems. These tests identify several systems which show potentially interesting transit timing variations (TTVs). Strong TTV systems have been valuable for the confirmation of planets and their mass measurements. Many of the systems identified in this study should prove fruitful for detailed TTV studies.

Potential market for novel tuberculosis diagnostics: worth the investment?

PubMed

Kik, Sandra V; Denkinger, Claudia M; Jefferson, Carole; Ginnard, Janet; Pai, Madhukar

2015-04-01

The potential available market (PAM) for new diagnostics for tuberculosis that meet the specifications of the high-priority target product profiles (TPPs) is currently unknown. We estimated the PAM in 2020 in 4 high-burden countries (South Africa, Brazil, China, and India) for tests that meet the specifications outlined in the TPPs. The yearly PAM was estimated for the most likely application of each TPP. In 2020 the PAM for all 4 countries together was estimated to be (1) 12M tests/year with a value of 48M-71M USD for a sputum smear-replacement test; (2) 16M tests/year with a value of 65M-97M USD for a biomarker test; (3) 18M tests/year with a value of 18M-35M USD for a triage test; (4) 12M tests/year with a value of 59M-2238M USD for a tuberculosis detection plus drug susceptibility test (DST) all-in-one or 1.5M tests/year for a DST that follows a positive tuberculosis detection test with a corresponding value of 75M-121M for both tuberculosis detection and DST. Although there is a considerable potential market for novel tuberculosis diagnostics that fit the specification of the TPPs in the 4 high-burden countries, the actual market for an individual product remains uncertain. © The Author 2014. Published by Oxford University Press on behalf of the Infectious Diseases Society of America. All rights reserved. For Permissions, please e-mail: journals.permissions@oup.com.

Undeclared Formaldehyde Levels in Patient Consumer Products: Formaldehyde Test Kit Utility.

PubMed

Ham, Jason E; Siegel, Paul; Maibach, Howard

2018-05-03

Formaldehyde allergic contact dermatitis (ACD) may be due to products with free formaldehyde or formaldehyde-releasing agents, however, assessment of formaldehyde levels in such products is infrequently conducted. The present study quantifies total releasable formaldehyde from "in-use" products associated with formaldehyde ACD and tests the utility of commercially available formaldehyde spot test kits. Personal care products from 2 patients with ACD to formaldehyde were initially screened at the clinic for formaldehyde using a formaldehyde spot test kit. Formaldehyde positive products were sent to the laboratory for confirmation by gas chromatography-mass spectrometry. In addition, 4 formaldehyde spot test kits were evaluated for potential utility in a clinical setting. Nine of the 10 formaldehyde spot test kit positive products obtained from formaldehyde allergic patients had formaldehyde with total releasable formaldehyde levels ranging from 5.4 to 269.4 µg/g. Of these, only 2 shampoos tested listed a formaldehyde-releasing agent in the ingredients or product literature. Subsequently, commercially available formaldehyde spot test kits were evaluated in the laboratory for ability to identify formaldehyde in personal care products. Chemical based formaldehyde spot test were more reliable than the enzymatic based test in identifying product releasable formaldehyde content. It is concluded that product labeled ingredient lists and available information are often inadequate to confirm the potential for formaldehyde exposure and chemical based spot test kits may have utility for identification of potential formaldehyde exposure from personal care products.

Not Only Jumps, Slumps, but Also "Mini Plateau." Creative Potential Assessed by the Test for Creative Thinking-Drawing Production. A Cross-Sectional Study of Polish Students Aged from 7 to 18

ERIC Educational Resources Information Center

Jastrzebska, Dominika; Limont, Wieslawa

2017-01-01

The purpose of this cross-sectional study was to examine the developmental trajectory of creative potentials of Polish students. A total of 1,522 Polish students aged between 7 and 18 from lower and upper primary school, middle school, and high school participated in the study. Creative potential was measured by means of the Test for Creative…

Auditory evoked potentials in two short-finned pilot whales (Globicephala macrorhynchus).

PubMed

Schlundt, Carolyn E; Dear, Randall L; Houser, Dorian S; Bowles, Ann E; Reidarson, Tom; Finneran, James J

2011-02-01

The hearing sensitivities of two short-finned pilot whales (Globicephala macrorhynchus) were investigated by measuring auditory evoked potentials generated in response to clicks and sinusoidal amplitude modulated (SAM) tones. The first whale tested, an adult female, was a long-time resident at SeaWorld San Diego with a known health history. Click-evoked responses in this animal were similar to those measured in other echolocating odontocetes. Auditory thresholds were comparable to dolphins of similar age determined with similar evoked potential methods. The region of best sensitivity was near 40 kHz and the upper limit of functional hearing was between 80 and 100 kHz. The second whale tested, a juvenile male, was recently stranded and deemed non-releasable. Click-evoked potentials were not detected in this animal and testing with SAM tones suggested severe hearing loss above 10 kHz.