Sample records for subsurface radioactive disposal

  1. Radioactive waste management complex low-level waste radiological composite analysis

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

    McCarthy, J.M.; Becker, B.H.; Magnuson, S.O.

    1998-05-01

    The composite analysis estimates the projected cumulative impacts to future members of the public from the disposal of low-level radioactive waste (LLW) at the Idaho National Engineering and Environmental Laboratory (INEEL) Radioactive Waste Management Complex (RWMC) and all other sources of radioactive contamination at the INEEL that could interact with the LLW disposal facility to affect the radiological dose. Based upon the composite analysis evaluation, waste buried in the Subsurface Disposal Area (SDA) at the RWMC is the only source at the INEEL that will significantly interact with the LLW facility. The source term used in the composite analysis consistsmore » of all historical SDA subsurface disposals of radionuclides as well as the authorized LLW subsurface disposal inventory and projected LLW subsurface disposal inventory. Exposure scenarios evaluated in the composite analysis include all the all-pathways and groundwater protection scenarios. The projected dose of 58 mrem/yr exceeds the composite analysis guidance dose constraint of 30 mrem/yr; therefore, an options analysis was conducted to determine the feasibility of reducing the projected annual dose. Three options for creating such a reduction were considered: (1) lowering infiltration of precipitation through the waste by providing a better cover, (2) maintaining control over the RWMC and portions of the INEEL indefinitely, and (3) extending the period of institutional control beyond the 100 years assumed in the composite analysis. Of the three options investigated, maintaining control over the RWMC and a small part of the present INEEL appears to be feasible and cost effective.« less

  2. 40 CFR 191.12 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... metric system which has been established by the International Bureau of Weights and Measures and is...) monitoring parameters related to disposal system performance. Annual committed effective dose means the... radioactive wastes in a disposal system; and (2) the subsurface underlying such a surface location. Disposal...

  3. 40 CFR 191.12 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... metric system which has been established by the International Bureau of Weights and Measures and is...) monitoring parameters related to disposal system performance. Annual committed effective dose means the... radioactive wastes in a disposal system; and (2) the subsurface underlying such a surface location. Disposal...

  4. 40 CFR 191.12 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... metric system which has been established by the International Bureau of Weights and Measures and is...) monitoring parameters related to disposal system performance. Annual committed effective dose means the... radioactive wastes in a disposal system; and (2) the subsurface underlying such a surface location. Disposal...

  5. Potential for microbial H2 and metal transformations associated with novel bacteria and archaea in deep terrestrial subsurface sediments.

    PubMed

    Hernsdorf, Alex W; Amano, Yuki; Miyakawa, Kazuya; Ise, Kotaro; Suzuki, Yohey; Anantharaman, Karthik; Probst, Alexander; Burstein, David; Thomas, Brian C; Banfield, Jillian F

    2017-08-01

    Geological sequestration in deep underground repositories is the prevailing proposed route for radioactive waste disposal. After the disposal of radioactive waste in the subsurface, H 2 may be produced by corrosion of steel and, ultimately, radionuclides will be exposed to the surrounding environment. To evaluate the potential for microbial activities to impact disposal systems, we explored the microbial community structure and metabolic functions of a sediment-hosted ecosystem at the Horonobe Underground Research Laboratory, Hokkaido, Japan. Overall, we found that the ecosystem hosted organisms from diverse lineages, including many from the phyla that lack isolated representatives. The majority of organisms can metabolize H 2 , often via oxidative [NiFe] hydrogenases or electron-bifurcating [FeFe] hydrogenases that enable ferredoxin-based pathways, including the ion motive Rnf complex. Many organisms implicated in H 2 metabolism are also predicted to catalyze carbon, nitrogen, iron and sulfur transformations. Notably, iron-based metabolism is predicted in a novel lineage of Actinobacteria and in a putative methane-oxidizing ANME-2d archaeon. We infer an ecological model that links microorganisms to sediment-derived resources and predict potential impacts of microbial activity on H 2 consumption and retardation of radionuclide migration.

  6. Movement of a tritium plume in shallow groundwater at a legacy low-level radioactive waste disposal site in eastern Australia.

    PubMed

    Hughes, C E; Cendón, D I; Harrison, J J; Hankin, S I; Johansen, M P; Payne, T E; Vine, M; Collins, R N; Hoffmann, E L; Loosz, T

    2011-10-01

    Between 1960 and 1968 low-level radioactive waste was buried in a series of shallow trenches near the Lucas Heights facility, south of Sydney, Australia. Groundwater monitoring carried out since the mid 1970s indicates that with the exception of tritium, no radioactivity above typical background levels has been detected outside the immediate vicinity of the trenches. The maximum tritium level detected in ground water was 390 kBq/L and the median value was 5400 Bq/L, decay corrected to the time of disposal. Since 1968, a plume of tritiated water has migrated from the disposal trenches and extends at least 100 m from the source area. Tritium in rainfall is negligible, however leachate from an adjacent and fill represents a significant additional tritium source. Study data indicate variation in concentration levels and plume distribution in response to wet and dry climatic periods and have been used to determine pathways for tritium migration through the subsurface.

  7. Potential for microbial H2 and metal transformations associated with novel bacteria and archaea in deep terrestrial subsurface sediments

    PubMed Central

    Hernsdorf, Alex W; Amano, Yuki; Miyakawa, Kazuya; Ise, Kotaro; Suzuki, Yohey; Anantharaman, Karthik; Probst, Alexander; Burstein, David; Thomas, Brian C; Banfield, Jillian F

    2017-01-01

    Geological sequestration in deep underground repositories is the prevailing proposed route for radioactive waste disposal. After the disposal of radioactive waste in the subsurface, H2 may be produced by corrosion of steel and, ultimately, radionuclides will be exposed to the surrounding environment. To evaluate the potential for microbial activities to impact disposal systems, we explored the microbial community structure and metabolic functions of a sediment-hosted ecosystem at the Horonobe Underground Research Laboratory, Hokkaido, Japan. Overall, we found that the ecosystem hosted organisms from diverse lineages, including many from the phyla that lack isolated representatives. The majority of organisms can metabolize H2, often via oxidative [NiFe] hydrogenases or electron-bifurcating [FeFe] hydrogenases that enable ferredoxin-based pathways, including the ion motive Rnf complex. Many organisms implicated in H2 metabolism are also predicted to catalyze carbon, nitrogen, iron and sulfur transformations. Notably, iron-based metabolism is predicted in a novel lineage of Actinobacteria and in a putative methane-oxidizing ANME-2d archaeon. We infer an ecological model that links microorganisms to sediment-derived resources and predict potential impacts of microbial activity on H2 consumption and retardation of radionuclide migration. PMID:28350393

  8. BLT-EC (Breach, Leach and Transport-Equilibrium Chemistry) data input guide. A computer model for simulating release and coupled geochemical transport of contaminants from a subsurface disposal facility

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

    MacKinnon, R.J.; Sullivan, T.M.; Kinsey, R.R.

    1997-05-01

    The BLT-EC computer code has been developed, implemented, and tested. BLT-EC is a two-dimensional finite element computer code capable of simulating the time-dependent release and reactive transport of aqueous phase species in a subsurface soil system. BLT-EC contains models to simulate the processes (container degradation, waste-form performance, transport, chemical reactions, and radioactive production and decay) most relevant to estimating the release and transport of contaminants from a subsurface disposal system. Water flow is provided through tabular input or auxiliary files. Container degradation considers localized failure due to pitting corrosion and general failure due to uniform surface degradation processes. Waste-form performancemore » considers release to be limited by one of four mechanisms: rinse with partitioning, diffusion, uniform surface degradation, and solubility. Transport considers the processes of advection, dispersion, diffusion, chemical reaction, radioactive production and decay, and sources (waste form releases). Chemical reactions accounted for include complexation, sorption, dissolution-precipitation, oxidation-reduction, and ion exchange. Radioactive production and decay in the waste form is simulated. To improve the usefulness of BLT-EC, a pre-processor, ECIN, which assists in the creation of chemistry input files, and a post-processor, BLTPLOT, which provides a visual display of the data have been developed. BLT-EC also includes an extensive database of thermodynamic data that is also accessible to ECIN. This document reviews the models implemented in BLT-EC and serves as a guide to creating input files and applying BLT-EC.« less

  9. Numerical modeling of subsurface radioactive solute transport from waste seepage ponds at the Idaho National Engineering Laboratory

    USGS Publications Warehouse

    Robertson, John B.

    1976-01-01

    Aqueous chemical and low-level radioactive effluents have been disposed to seepage ponds since 1952 at the Idaho National Engineering Laboratory. The solutions percolate toward the Snake River Plain aquifer (135 m below) through interlayered basalts and unconsolidated sediments and an extensive zone of ground water perched on a sedimentary layer about 40 m beneath the ponds. A three-segment numerical model was developed to simulate the system, including effects of convection, hydrodynamic dispersion, radioactive decay, and adsorption. Simulated hydraulics and solute migration patterns for all segments agree adequately with the available field data. The model can be used to project subsurface distributions of waste solutes under a variety of assumed conditions for the future. Although chloride and tritium reached the aquifer several years ago, the model analysis suggests that the more easily sorbed solutes, such as cesium-137 and strontium-90, would not reach the aquifer in detectable concentrations within 150 years for the conditions assumed. (Woodard-USGS)

  10. A Strategy to Conduct an Analysis of the Long-Term Performance of Low-Activity Waste Glass in a Shallow Subsurface Disposal System at Hanford

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

    Neeway, James J.; Pierce, Eric M.; Freedman, Vicky L.

    2014-08-04

    The federal facilities located on the Hanford Site in southeastern Washington State have been used extensively by the U.S. government to produce nuclear materials for the U.S. strategic defense arsenal. Currently, the Hanford Site is under the stewardship of the U.S. Department of Energy (DOE) Office of Environmental Management (EM). A large inventory of radioactive and mixed waste resulting from the production of nuclear materials has accumulated, mainly in 177 underground single- and double-shell tanks located in the central plateau of the Hanford Site (Mann et al., 2001). The DOE-EM Office of River Protection (ORP) is proceeding with plans tomore » immobilize and permanently dispose of the low-activity waste (LAW) fraction onsite in a shallow subsurface disposal facility (the Integrated Disposal Facility [IDF]). Pacific Northwest National Laboratory (PNNL) was contracted to provide the technical basis for estimating radionuclide release from the engineered portion of the IDF (the source term) as part of an immobilized low-activity waste (ILAW) glass testing program to support future IDF performance assessments (PAs).« less

  11. Geological Disposal of Radioactive Waste: A Long-Term Socio-Technical Experiment.

    PubMed

    Schröder, Jantine

    2016-06-01

    In this article we investigate whether long-term radioactive waste management by means of geological disposal can be understood as a social experiment. Geological disposal is a rather particular technology in the way it deals with the analytical and ethical complexities implied by the idea of technological innovation as social experimentation, because it is presented as a technology that ultimately functions without human involvement. We argue that, even when the long term function of the 'social' is foreseen to be restricted to safeguarding the functioning of the 'technical', geological disposal is still a social experiment. In order to better understand this argument and explore how it could be addressed, we elaborate the idea of social experimentation with the notion of co-production and the analytical tools of delegation, prescription and network as developed by actor-network theory. In doing so we emphasize that geological disposal inherently involves relations between surface and subsurface, between humans and nonhumans, between the social, material and natural realm, and that these relations require recognition and further elaboration. In other words, we argue that geological disposal concurrently is a social and a technical experiment, or better, a long-term socio-technical experiment. We end with proposing the idea of 'actor-networking' as a sensitizing concept for future research into what geological disposal as a socio-technical experiment could look like.

  12. Subsurface waste disposal by means of wells - A selective annotated bibliography

    USGS Publications Warehouse

    Rima, Donald Robert; Chase, Edith B.; Myers, Beverly M.

    1971-01-01

    Subsurface waste disposal by means of wells is the practice of using drilled wells to inject unwanted substances into underground rock formations. The use of wells for this purpose is not a new idea. As long ago as the end of the last century, it was common practice to drill wells for the express purpose of draining swamps and small lakes to reclaim the land for agricultural purposes. A few decades later in the 1920's and 1930's many oil companies began using injection wells to dispose of oil-field brines and to repressurize oil reservoirs. During World War II, the Atomic Energy Commission began using injection wells to dispose of certain types of radioactive wastes. More recently, injection wells have been drilled to dispose of a variety of byproducts of industrial processes. The number of such wells has increased rapidly since Congress passed the Clean Streams Act of 1966, which restricted the discharge of waste into surface waters.Many scientists and public officials question the propriety of using the term "disposal" when referring to the underground injection of wastes. Their reasons are that underground injection is not, as many advocates claim, "a complete and final answer" to the waste-disposal problem. Rather, it is merely a process wherein the injected wastes are committed to the subsurface with uncertainty as to their ultimate fate or limits of confinement. In effect, the wastes, undiminished and unchanged, are removed from the custody of man and placed in the custody of nature.Although the concept of waste-injection wells is relatively simple, the effects of waste injection can be very complex, particularly when dealing with the exotic and complex components of some industrial wastes. Besides the physical forces of injection, there are many varied interactions between the injected wastes and the materials within the injection zone. Because these changes occur out of sight in the subsurface, they are difficult to assess and not generally understood. In addition, the various aspects of the problem involve a wide spectrum of science and engineering. Hence, articles published on the subject are widely dispersed in the technical and scientific literature. 

  13. Method for Implementing Subsurface Solid Derived Concentration Guideline Levels (DCGL) - 12331

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

    Lively, J.W.

    2012-07-01

    The U.S. Nuclear Regulatory Commission (NRC) and other federal agencies currently approve the Multi-Agency Radiation Site Survey and Investigation Manual (MARSSIM) as guidance for licensees who are conducting final radiological status surveys in support of decommissioning. MARSSIM provides a method to demonstrate compliance with the applicable regulation by comparing residual radioactivity in surface soils with derived concentration guideline levels (DCGLs), but specifically discounts its applicability to subsurface soils. Many sites and facilities undergoing decommissioning contain subsurface soils that are potentially impacted by radiological constituents. In the absence of specific guidance designed to address the derivation of subsurface soil DCGLs andmore » compliance demonstration, decommissioning facilities have attempted to apply DCGLs and final status survey techniques designed specifically for surface soils to subsurface soils. The decision to apply surface soil limits and surface soil compliance metrics to subsurface soils typically results in significant over-excavation with associated cost escalation. MACTEC, Inc. has developed the overarching concepts and principles found in recent NRC decommissioning guidance in NUREG 1757 to establish a functional method to derive dose-based subsurface soil DCGLs. The subsurface soil method developed by MACTEC also establishes a rigorous set of criterion-based data evaluation metrics (with analogs to the MARSSIM methodology) that can be used to demonstrate compliance with the developed subsurface soil DCGLs. The method establishes a continuum of volume factors that relate the size and depth of a volume of subsurface soil having elevated concentrations of residual radioactivity with its ability to produce dose. The method integrates the subsurface soil sampling regime with the derivation of the subsurface soil DCGL such that a self-regulating optimization is naturally sought by both the responsible party and regulator. This paper describes the concepts and basis used by MACTEC to develop the dose-based subsurface soil DCGL method. The paper will show how MACTEC's method can be used to demonstrate that higher concentrations of residual radioactivity in subsurface soils (as compared with surface soils) can meet the NRC's dose-based regulations. MACTEC's method has been used successfully to obtain the NRC's radiological release at a site with known radiological impacts to subsurface soils exceeding the surface soil DCGL, saving both time and cost. Having considered the current NRC guidance for consideration of residual radioactivity in subsurface soils during decommissioning, MACTEC has developed a technically based approach to the derivation of and demonstration of compliance with subsurface soil DCGLs for radionuclides. In fact, the process uses the already accepted concepts and metrics approved for surface soils as the foundation for deriving scaling factors used to calculate subsurface soil DCGLs that are at least equally protective of the decommissioning annual dose standard. Each of the elements identified for consideration in the current NRC guidance is addressed in this proposed method. Additionally, there is considerable conservatism built into the assumptions and techniques used to arrive at subsurface soil scaling factors and DCGLs. The degree of conservatism embodied in the approach used is such that risk managers and decision makers approving and using subsurface soil DCGLs derived in accordance with this method can be confident that the future exposures will be well below permissible and safe levels. The technical basis for the method can be applied to a broad variety of sites with residual radioactivity in subsurface soils. Given the costly nature of soil surveys, excavation, and disposal of soils as low-level radioactive waste, MACTEC's method for deriving and demonstrating compliance with subsurface soil DCGLs offers the possibility of significant cost savings over the traditional approach of applying surface soil DCGLs to subsurface soils. Furthermore, while yet untested, MACTEC believes that the concepts and methods embodied in this approach could readily be applied to other types of contamination found in subsurface soils. (author)« less

  14. A minimalistic microbial food web in an excavated deep subsurface clay rock.

    PubMed

    Bagnoud, Alexandre; de Bruijn, Ino; Andersson, Anders F; Diomidis, Nikitas; Leupin, Olivier X; Schwyn, Bernhard; Bernier-Latmani, Rizlan

    2016-01-01

    Clay rocks are being considered for radioactive waste disposal, but relatively little is known about the impact of microbes on the long-term safety of geological repositories. Thus, a more complete understanding of microbial community structure and function in these environments would provide further detail for the evaluation of the safety of geological disposal of radioactive waste in clay rocks. It would also provide a unique glimpse into a poorly studied deep subsurface microbial ecosystem. Previous studies concluded that microorganisms were present in pristine Opalinus Clay, but inactive. In this work, we describe the microbial community and assess the metabolic activities taking place within borehole water. Metagenomic sequencing and genome-binning of a porewater sample containing suspended clay particles revealed a remarkably simple heterotrophic microbial community, fueled by sedimentary organic carbon, mainly composed of two organisms: a Pseudomonas sp. fermenting bacterium growing on organic macromolecules and releasing organic acids and H2, and a sulfate-reducing Peptococcaceae able to oxidize organic molecules to CO(2). In Opalinus Clay, this microbial system likely thrives where pore space allows it. In a repository, this may occur where the clay rock has been locally damaged by excavation or in engineered backfills. © FEMS 2015. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com.

  15. Geochemical Data Package for Performance Assessment Calculations Related to the Savannah River Site

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

    Kaplan, Daniel I.

    The Savannah River Site (SRS) disposes of low-level radioactive waste (LLW) and stabilizes high-level radioactive waste (HLW) tanks in the subsurface environment. Calculations used to establish the radiological limits of these facilities are referred to as Performance Assessments (PA), Special Analyses (SA), and Composite Analyses (CA). The objective of this document is to revise existing geochemical input values used for these calculations. This work builds on earlier compilations of geochemical data (2007, 2010), referred to a geochemical data packages. This work is being conducted as part of the on-going maintenance program of the SRS PA programs that periodically updates calculationsmore » and data packages when new information becomes available. Because application of values without full understanding of their original purpose may lead to misuse, this document also provides the geochemical conceptual model, the approach used for selecting the values, the justification for selecting data, and the assumptions made to assure that the conceptual and numerical geochemical models are reasonably conservative (i.e., bias the recommended input values to reflect conditions that will tend to predict the maximum risk to the hypothetical recipient). This document provides 1088 input parameters for geochemical parameters describing transport processes for 64 elements (>740 radioisotopes) potentially occurring within eight subsurface disposal or tank closure areas: Slit Trenches (ST), Engineered Trenches (ET), Low Activity Waste Vault (LAWV), Intermediate Level (ILV) Vaults, Naval Reactor Component Disposal Areas (NRCDA), Components-in-Grout (CIG) Trenches, Saltstone Facility, and Closed Liquid Waste Tanks. The geochemical parameters described here are the distribution coefficient, Kd value, apparent solubility concentration, k s value, and the cementitious leachate impact factor.« less

  16. Radioactive Waste Management Complex low-level waste radiological performance assessment

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

    Maheras, S.J.; Rood, A.S.; Magnuson, S.O.

    This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsitemore » receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected.« less

  17. Project Execution Plan for the Remote Handled Low-Level Waste Disposal Project

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

    Danny Anderson

    2014-07-01

    As part of ongoing cleanup activities at the Idaho National Laboratory (INL), closure of the Radioactive Waste Management Complex (RWMC) is proceeding under the Comprehensive Environmental Response, Compensation, and Liability Act (42 USC 9601 et seq. 1980). INL-generated radioactive waste has been disposed of at RWMC since 1952. The Subsurface Disposal Area (SDA) at RWMC accepted the bulk of INL’s contact and remote-handled low-level waste (LLW) for disposal. Disposal of contact-handled LLW and remote-handled LLW ion-exchange resins from the Advanced Test Reactor in the open pit of the SDA ceased September 30, 2008. Disposal of remote-handled LLW in concrete disposalmore » vaults at RWMC will continue until the facility is full or until it must be closed in preparation for final remediation of the SDA (approximately at the end of fiscal year FY 2017). The continuing nuclear mission of INL, associated ongoing and planned operations, and Naval spent fuel activities at the Naval Reactors Facility (NRF) require continued capability to appropriately dispose of contact and remote handled LLW. A programmatic analysis of disposal alternatives for contact and remote-handled LLW generated at INL was conducted by the INL contractor in Fiscal Year 2006; subsequent evaluations were completed in Fiscal Year 2007. The result of these analyses was a recommendation to the Department of Energy (DOE) that all contact-handled LLW generated after September 30, 2008, be disposed offsite, and that DOE proceed with a capital project to establish replacement remote-handled LLW disposal capability. An analysis of the alternatives for providing replacement remote-handled LLW disposal capability has been performed to support Critical Decision-1. The highest ranked alternative to provide this required capability has been determined to be the development of a new onsite remote-handled LLW disposal facility to replace the existing remote-handled LLW disposal vaults at the SDA. Several offsite DOE and commercial disposal options exist for contact-handled LLW; however, offsite disposal options are either not currently available (i.e., commercial disposal facilities), practical, or cost-effective for all remote-handled LLW streams generated at INL. Offsite disposal of all INL and tenant-generated remote-handled waste is further complicated by issues associated with transporting highly radioactive waste in commerce; and infrastructure and processing changes at the generating facilities, specifically NRF, that would be required to support offsite disposal. The INL Remote-Handled LLW Disposal Project will develop a new remote handled LLW disposal facility to meet mission-critical, remote-handled LLW disposal needs. A formal DOE decision to proceed with the project has been made in accordance with the requirements of National Environmental Policy Act (42 USC§ 4321 et seq.). Remote-handled LLW is generated from nuclear programs conducted at INL, including spent nuclear fuel handling and operations at NRF and operations at the Advanced Test Reactor. Remote-handled LLW also will be generated by new INL programs and from segregation and treatment (as necessary) of remote handled scrap and waste currently stored in the Radioactive Scrap and Waste Facility at the Materials and Fuels Complex.« less

  18. On Subsurface Fracture Opening and Closure

    NASA Astrophysics Data System (ADS)

    Wang, Y.

    2016-12-01

    Mechanistic understanding of fracture opening and closure in geologic media is of significant importance to nature resource extraction and waste management, such as geothermal energy extraction, oil/gas production, radioactive waste disposal, and carbon sequestration and storage). A dynamic model for subsurface fracture opening and closure has been formulated. The model explicitly accounts for the stress concentration around individual aperture channels and the stress-activated mineral dissolution and precipitation. A preliminary model analysis has demonstrated the importance of the stress-activated dissolution mechanism in the evolution of fracture aperture in a stressed geologic medium. The model provides a reasonable explanation for some key features of fracture opening and closure observed in laboratory experiments, including a spontaneous switch from a net permeability reduction to a net permeability increase with no changes in a limestone fracture experiment.

  19. Coupling Legacy and Contemporary Deterministic Codes to Goldsim for Probabilistic Assessments of Potential Low-Level Waste Repository Sites

    NASA Astrophysics Data System (ADS)

    Mattie, P. D.; Knowlton, R. G.; Arnold, B. W.; Tien, N.; Kuo, M.

    2006-12-01

    Sandia National Laboratories (Sandia), a U.S. Department of Energy National Laboratory, has over 30 years experience in radioactive waste disposal and is providing assistance internationally in a number of areas relevant to the safety assessment of radioactive waste disposal systems. International technology transfer efforts are often hampered by small budgets, time schedule constraints, and a lack of experienced personnel in countries with small radioactive waste disposal programs. In an effort to surmount these difficulties, Sandia has developed a system that utilizes a combination of commercially available codes and existing legacy codes for probabilistic safety assessment modeling that facilitates the technology transfer and maximizes limited available funding. Numerous codes developed and endorsed by the United States Nuclear Regulatory Commission and codes developed and maintained by United States Department of Energy are generally available to foreign countries after addressing import/export control and copyright requirements. From a programmatic view, it is easier to utilize existing codes than to develop new codes. From an economic perspective, it is not possible for most countries with small radioactive waste disposal programs to maintain complex software, which meets the rigors of both domestic regulatory requirements and international peer review. Therefore, re-vitalization of deterministic legacy codes, as well as an adaptation of contemporary deterministic codes, provides a creditable and solid computational platform for constructing probabilistic safety assessment models. External model linkage capabilities in Goldsim and the techniques applied to facilitate this process will be presented using example applications, including Breach, Leach, and Transport-Multiple Species (BLT-MS), a U.S. NRC sponsored code simulating release and transport of contaminants from a subsurface low-level waste disposal facility used in a cooperative technology transfer project between Sandia National Laboratories and Taiwan's Institute of Nuclear Energy Research (INER) for the preliminary assessment of several candidate low-level waste repository sites. Sandia National Laboratories is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy under Contract DE AC04 94AL85000.

  20. Mechanical environmental transport of actinides and ¹³⁷Cs from an arid radioactive waste disposal site.

    PubMed

    Snow, Mathew S; Clark, Sue B; Morrison, Samuel S; Watrous, Matthew G; Olson, John E; Snyder, Darin C

    2015-10-01

    Aeolian and pluvial processes represent important mechanisms for the movement of actinides and fission products at the Earth's surface. Soil samples taken in the early 1970's near a Department of Energy radioactive waste disposal site (the Subsurface Disposal Area, SDA, located in southeastern Idaho) provide a case study for studying the mechanisms and characteristics of environmental actinide and (137)Cs transport in an arid environment. Multi-component mixing models suggest actinide contamination within 2.5 km of the SDA can be described by mixing between 2 distinct SDA end members and regional nuclear weapons fallout. The absence of chemical fractionation between (241)Am and (239+240)Pu with depth for samples beyond the northeastern corner and lack of (241)Am in-growth over time (due to (241)Pu decay) suggest mechanical transport and mixing of discrete contaminated particles under arid conditions. Occasional samples northeast of the SDA (the direction of the prevailing winds) contain anomalously high concentrations of Pu with (240)Pu/(239)Pu isotopic ratios statistically identical to those in the northeastern corner. Taken together, these data suggest flooding resulted in mechanical transport of contaminated particles into the area between the SDA and a flood containment dike in the northeastern corner, following which subsequent contamination spreading in the northeastern direction resulted from wind transport of discrete particles. Copyright © 2015 Elsevier Ltd. All rights reserved.

  1. Geologic and geophysical characterization studies of Yucca Mountain, Nevada, a potential high-level radioactive-waste repository

    USGS Publications Warehouse

    Whitney, J.W.; Keefer, W.R.

    2000-01-01

    In recognition of a critical national need for permanent radioactive-waste storage, Yucca Mountain in southwestern Nevada has been investigated by Federal agencies since the 1970's, as a potential geologic disposal site. In 1987, Congress selected Yucca Mountain for an expanded and more detailed site characterization effort. As an integral part of this program, the U.S. Geological Survey began a series of detailed geologic, geophysical, and related investigations designed to characterize the tectonic setting, fault behavior, and seismicity of the Yucca Mountain area. This document presents the results of 13 studies of the tectonic environment of Yucca Mountain, in support of a broad goal to assess the effects of future seismic and fault activity in the area on design, long-term performance, and safe operation of the potential surface and subsurface repository facilities.

  2. 10 CFR 51.62 - Environmental report-land disposal of radioactive waste licensed under 10 CFR part 61.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Environmental report-land disposal of radioactive waste....62 Environmental report—land disposal of radioactive waste licensed under 10 CFR part 61. (a) Each applicant for issuance of a license for land disposal of radioactive waste pursuant to part 61 of this...

  3. 10 CFR 51.62 - Environmental report-land disposal of radioactive waste licensed under 10 CFR part 61.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Environmental report-land disposal of radioactive waste....62 Environmental report—land disposal of radioactive waste licensed under 10 CFR part 61. (a) Each applicant for issuance of a license for land disposal of radioactive waste pursuant to part 61 of this...

  4. 10 CFR 51.62 - Environmental report-land disposal of radioactive waste licensed under 10 CFR part 61.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Environmental report-land disposal of radioactive waste....62 Environmental report—land disposal of radioactive waste licensed under 10 CFR part 61. (a) Each applicant for issuance of a license for land disposal of radioactive waste pursuant to part 61 of this...

  5. 10 CFR 51.62 - Environmental report-land disposal of radioactive waste licensed under 10 CFR part 61.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Environmental report-land disposal of radioactive waste....62 Environmental report—land disposal of radioactive waste licensed under 10 CFR part 61. (a) Each applicant for issuance of a license for land disposal of radioactive waste pursuant to part 61 of this...

  6. 10 CFR 51.62 - Environmental report-land disposal of radioactive waste licensed under 10 CFR part 61.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Environmental report-land disposal of radioactive waste....62 Environmental report—land disposal of radioactive waste licensed under 10 CFR part 61. (a) Each applicant for issuance of a license for land disposal of radioactive waste pursuant to part 61 of this...

  7. Regulatory controls on the hydrogeological characterization of a mixed waste disposal site, Radioactive Waste Management Complex, Idaho National Engineering Laboratory

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

    Ruebelmann, K.L.

    1990-01-01

    Following the detection of chlorinated volatile organic compounds in the groundwater beneath the SDA in the summer of 1987, hydrogeological characterization of the Radioactive Waste Management Complex (RWMC), Idaho National Engineering Laboratory (INEL) was required by the Resource Conservation and Recovery Act (RCRA). The waste site, the Subsurface Disposal Area (SDA), is the subject of a RCRA Corrective Action Program. Regulatory requirements for the Corrective Action Program dictate a phased approach to evaluation of the SDA. In the first phase of the program, the SDA is the subject of a RCRA Facility Investigation (RIF), which will obtain information to fullymore » characterize the physical properties of the site, determine the nature and extent of contamination, and identify pathways for migration of contaminants. If the need for corrective measures is identified during the RIF, a Corrective Measures Study (CMS) will be performed as second phase. Information generated during the RIF will be used to aid in the selection and implementation of appropriate corrective measures to correct the release. Following the CMS, the final phase is the implementation of the selected corrective measures. 4 refs., 1 fig.« less

  8. 10 CFR 62.2 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    .... Emergency access means access to an operating non-Federal or regional low-level radioactive waste disposal... regional low-level radioactive waste disposal facility or facilities for a period not to exceed 180 days... waste. Non-Federal disposal facility means a low-level radioactive waste disposal facility that is...

  9. ASSESSMENT OF RADIOACTIVE AND NON-RADIOACTIVE CONTAMINANTS FOUND IN LOW LEVEL RADIOACTIVE WASTE STREAMS

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

    R.H. Little, P.R. Maul, J.S.S. Penfoldag

    2003-02-27

    This paper describes and presents the findings from two studies undertaken for the European Commission to assess the long-term impact upon the environment and human health of non-radioactive contaminants found in various low level radioactive waste streams. The initial study investigated the application of safety assessment approaches developed for radioactive contaminants to the assessment of nonradioactive contaminants in low level radioactive waste. It demonstrated how disposal limits could be derived for a range of non-radioactive contaminants and generic disposal facilities. The follow-up study used the same approach but undertook more detailed, disposal system specific calculations, assessing the impacts of bothmore » the non-radioactive and radioactive contaminants. The calculations undertaken indicated that it is prudent to consider non-radioactive, as well as radioactive contaminants, when assessing the impacts of low level radioactive waste disposal. For some waste streams with relatively low concentrations of radionuclides, the potential post-closure disposal impacts from non-radioactive contaminants can be comparable with the potential radiological impacts. For such waste streams there is therefore an added incentive to explore options for recycling the materials involved wherever possible.« less

  10. The status of LILW disposal facility construction in Korea

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

    Kim, Min-Seok; Chung, Myung-Sub; Park, Kyu-Wan

    2013-07-01

    In this paper, we discuss the experiences during the construction of the first LILW disposal facility in South Korea. In December 2005, the South Korean Government designated Gyeongju-city as a host city of Low- and Intermediate-Level Radioactive Waste(LILW) disposal site through local referendums held in regions whose local governments had applied to host disposal facility in accordance with the site selection procedures. The LILW disposal facility is being constructed in Bongilri, Yangbuk-myeon, Gyeongju. The official name of the disposal facility is called 'Wolsong Low and Intermediate Level Radioactive Waste Disposal Center (LILW Disposal Center)'. It can dispose of 800,000 drumsmore » of radioactive wastes in a site of 2,100,000 square meters. At the first stage, LILW repository of underground silo type with disposal capacity of 100,000 drums is under construction expected to be completed by June of 2014. The Wolsong Low and Intermediate Level Radioactive Waste Disposal Center consists of surface facilities and underground facilities. The surface facilities include a reception and inspection facility, an interim storage facility, a radioactive waste treatment building, and supporting facilities such as main control center, equipment and maintenance shop. The underground facilities consist of a construction tunnel for transport of construction equipment and materials, an operation tunnel for transport of radioactive waste, an entrance shaft for workers, and six silos for final disposal of radioactive waste. As of Dec. 2012, the overall project progress rate is 93.8%. (authors)« less

  11. Influences of specific ions in groundwater on concrete degradation in subsurface engineered barrier system.

    PubMed

    Lin, Wen-Sheng; Liu, Chen-Wuing; Li, Ming-Hsu

    2016-01-01

    Many disposal concepts currently show that concrete is an effective confinement material used in engineered barrier systems (EBS) at a number of low-level radioactive waste (LLW) disposal sites. Cement-based materials have properties for the encapsulation, isolation, or retardation of a variety of hazardous contaminants. The reactive chemical transport model of HYDROGEOCHEM 5.0 was applied to simulate the effect of hydrogeochemical processes on concrete barrier degradation in an EBS which has been proposed to use in the LLW disposal site in Taiwan. The simulated results indicated that the main processes that are responsible for concrete degradation are the species induced from hydrogen ion, sulfate, and chloride. The EBS with the side ditch drainage system effectively discharges the infiltrated water and lowers the solute concentrations that may induce concrete degradation. The redox processes markedly influence the formations of the degradation materials. The reductive environment in the EBS reduces the formation of ettringite in concrete degradation processes. Moreover, the chemical conditions in the concrete barriers maintain an alkaline condition after 300 years in the proposed LLW repository. This study provides a detailed picture of the long-term evolution of the hydrogeochemical environment in the proposed LLW disposal site in Taiwan.

  12. The biogeochemical fate of nickel during microbial ISA degradation; implications for nuclear waste disposal.

    PubMed

    Kuippers, Gina; Boothman, Christopher; Bagshaw, Heath; Ward, Michael; Beard, Rebecca; Bryan, Nicholas; Lloyd, Jonathan R

    2018-06-08

    Intermediate level radioactive waste (ILW) generally contains a heterogeneous range of organic and inorganic materials, of which some are encapsulated in cement. Of particular concern are cellulosic waste items, which will chemically degrade under the conditions predicted during waste disposal, forming significant quantities of isosaccharinic acid (ISA), a strongly chelating ligand. ISA therefore has the potential to increase the mobility of a wide range of radionuclides via complex formation, including Ni-63 and Ni-59. Although ISA is known to be metabolized by anaerobic microorganisms, the biodegradation of metal-ISA complexes remains unexplored. This study investigates the fate of a Ni-ISA complex in Fe(III)-reducing enrichment cultures at neutral pH, representative of a microbial community in the subsurface. After initial sorption of Ni onto Fe(III)oxyhydroxides, microbial ISA biodegradation resulted in >90% removal of the remaining Ni from solution when present at 0.1 mM, whereas higher concentrations of Ni proved toxic. The microbial consortium associated with ISA degradation was dominated by close relatives to Clostridia and Geobacter species. Nickel was preferentially immobilized with trace amounts of biogenic amorphous iron sulfides. This study highlights the potential for microbial activity to help remove chelating agents and radionuclides from the groundwater in the subsurface geosphere surrounding a geodisposal facility.

  13. Disposal of low-level radioactive waste. Impact on the medical profession

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

    Brill, D.R.; Allen, E.W.; Lutzker, L.G.

    1985-11-01

    During 1985, low-level radioactive waste disposal has become a critical concern. The issue has been forced by the threatened closure of the three commercial disposal sites. The medical community has used radioactive isotopes for decades in nuclear medicine, radiation therapy, radioimmunoassay, and biomedical research. Loss of disposal capacity for radioactive wastes generated by these activities, by the suppliers of radioisotopes, and by pharmaceutical companies will have a profound impact on the medical profession.

  14. 10 CFR 61.2 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.... Disposal site means that portion of a land disposal facility which is used for disposal of waste. It... facility means a land disposal facility in which radioactive waste is disposed of in or within the upper 30...

  15. 10 CFR 61.2 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.... Disposal site means that portion of a land disposal facility which is used for disposal of waste. It... facility means a land disposal facility in which radioactive waste is disposed of in or within the upper 30...

  16. 10 CFR 61.2 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.... Disposal site means that portion of a land disposal facility which is used for disposal of waste. It... facility means a land disposal facility in which radioactive waste is disposed of in or within the upper 30...

  17. 10 CFR 61.2 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.... Disposal site means that portion of a land disposal facility which is used for disposal of waste. It... facility means a land disposal facility in which radioactive waste is disposed of in or within the upper 30...

  18. 10 CFR 61.2 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.... Disposal site means that portion of a land disposal facility which is used for disposal of waste. It... facility means a land disposal facility in which radioactive waste is disposed of in or within the upper 30...

  19. 10 CFR 61.7 - Concepts.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.7 Concepts. (a) The disposal facility. (1) Part 61 is intended to apply to land disposal of... specific technical requirements for near-surface disposal of radioactive waste, a subset of land disposal...

  20. 10 CFR 61.7 - Concepts.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.7 Concepts. (a) The disposal facility. (1) Part 61 is intended to apply to land disposal of... specific technical requirements for near-surface disposal of radioactive waste, a subset of land disposal...

  1. 10 CFR 61.7 - Concepts.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.7 Concepts. (a) The disposal facility. (1) Part 61 is intended to apply to land disposal of... specific technical requirements for near-surface disposal of radioactive waste, a subset of land disposal...

  2. 10 CFR 61.7 - Concepts.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.7 Concepts. (a) The disposal facility. (1) Part 61 is intended to apply to land disposal of... specific technical requirements for near-surface disposal of radioactive waste, a subset of land disposal...

  3. 10 CFR 61.7 - Concepts.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.7 Concepts. (a) The disposal facility. (1) Part 61 is intended to apply to land disposal of... specific technical requirements for near-surface disposal of radioactive waste, a subset of land disposal...

  4. High-Level Radioactive Waste: Safe Storage and Ultimate Disposal.

    ERIC Educational Resources Information Center

    Dukert, Joseph M.

    Described are problems and techniques for safe disposal of radioactive waste. Degrees of radioactivity, temporary storage, and long-term permanent storage are discussed. Included are diagrams of estimated waste volumes to the year 2000 and of an artist's conception of a permanent underground disposal facility. (SL)

  5. Salmon Site Remedial Investigation Report, Exhibit 5

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

    USDOE /NV

    1999-09-01

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides intomore » the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the installation of a water supply system that will provide potable water to the site and residence in the proximity to the site; (2) continued maintenance of surface institutional controls and subsurface restrictions; and (3) continue to implement the long-term hydrologic monitoring program. The Salmon Site will be relinquished the State of Mississippi as mandated by Public Law 104-201-September 23, 1996, to be used as a demonstration forest/wildlife refuge. Should the land use change in the future and/or monitoring information indicates a change in the site conditions, the DOE will reassess the risk impacts to human health and the environment.« less

  6. Salmon Site Remedial Investigation Report, Main Body

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

    US DOE /NV

    1999-09-01

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides intomore » the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the installation of a water supply system that will provide potable water to the site and residence in the proximity to the site; (2) continued maintenance of surface institutional controls and subsurface restrictions; and (3) continue to implement the long-term hydrologic monitoring program. The Salmon Site will be relinquished the State of Mississippi as mandated by Public Law 104-201-September 23, 1996, to be used as a demonstration forest/wildlife refuge. Should the land use change in the future and/or monitoring information indicates a change in the site conditions, the DOE will reassess the risk impacts to human health and the environment.« less

  7. Salmon Site Remedial Investigation Report, Exhibit 2

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

    USDOE NV

    1999-09-01

    This Salmon Site Remedial Investigation Report provides the results of activities initiated by the U.S. Department of Energy (DOE) to determine if contamination at the Salmon Site poses a current or future risk to human health and the environment. These results were used to develop and evaluate a range of risk-based remedial alternatives. Located in Lamar County, Mississippi, the Salmon Site was used by the U.S. Atomic Energy Commission (predecessor to the DOE) between 1964 and 1970 for two nuclear and two gas explosions conducted deep underground in a salt dome. The testing resulted in the release of radionuclides intomore » the salt dome. During reentry drilling and other site activities, liquid and solid wastes containing radioactivity were generated resulting in surface soil and groundwater contamination. Most of the waste and contaminated soil and water were disposed of in 1993 during site restoration either in the cavities left by the tests or in an injection well. Other radioactive wastes were transported to the Nevada Test Site for disposal. Nonradioactive wastes were disposed of in pits at the site and capped with clean soil and graded. The preliminary investigation showed residual contamination in the Surface Ground Zero mud pits below the water table. Remedial investigations results concluded the contaminant concentrations detected present no significant risk to existing and/or future land users, if surface institutional controls and subsurface restrictions are maintained. Recent sampling results determined no significant contamination in the surface or shallow subsurface. The test cavity resulting from the experiments is contaminated and cannot be economically remediated with existing technologies. The ecological sampling did not detect biological uptake of contaminants in the plants or animals sampled. Based on the current use of the Salmon Site, the following remedial actions were identified to protect both human health and the environment: (1) the installation of a water supply system that will provide potable water to the site and residence in the proximity to the site; (2) continued maintenance of surface institutional controls and subsurface restrictions; and (3) continue to implement the long-term hydrologic monitoring program. The Salmon Site will be relinquished the State of Mississippi as mandated by Public Law 104-201-September 23, 1996, to be used as a demonstration forest/wildlife refuge. Should the land use change in the future and/or monitoring information indicates a change in the site conditions, the DOE will reassess the risk impacts to human health and the environment.« less

  8. Tailings Pond Characterization And Designing Through Geophysical Surveys In Dipping Sedimentary Formations

    NASA Astrophysics Data System (ADS)

    Muralidharan, D.; Andrade, R.; Anand, K.; Sathish, R.; Goud, K.

    2009-12-01

    Mining activities results into generation of disintegrated waste materials attaining increased mobilization status and requires a safe disposal mechanism through back filling process or secluded storage on surface with prevention of its interaction with environment cycle. The surface disposal of waste materials will become more critical in case of mined minerals having toxic or radioactive elements. In such cases, the surface disposal site is to be characterized for its sub-surface nature to understand its role in environmental impact due to the loading of waste materials. Near surface geophysics plays a major role in mapping the geophysical characters of the sub-surface formations in and around the disposal site and even to certain extent helps in designing of the storage structure. Integrated geophysical methods involving resistivity tomography, ground magnetic and shallow seismic studies were carried out over proposed tailings pond area of 0.3 sq. kms underlined by dipping sedimentary rocks consisting of ferruginous shales and dolomitic to siliceous limestone with varying thicknesses. The investigated site being located in tectonically disturbed area, geophysical investigations were carried out with number of profiles to visualize the sub-surface nature with clarity. The integration of results of twenty profiles of resistivity tomography with 2 m (shallow) and 10 m (moderate depth) electrode spacing’s enabled in preparing probable sub-surface geological section along the strike direction of the formation under the tailings pond with some geo-tectonic structure inferred to be a fault. Similarly, two resistivity tomography profiles perpendicular to the strike direction of the formations brought out the existence of buried basic intrusive body on the northern boundary of the proposed tailings pond. Two resistivity tomography profiles in criss-cross direction over the suspected fault zone confirmed fault existence on the north-eastern part of tailings pond. Thirty two magnetic profiles inside the tailings pond and surrounding areas on the southern part of the tailings pond enabled in identifying two parallel east-west intrusive bodies forming the impermeable boundary for the tailings pond. The shallow seismic refraction and the geophysical studies in and around the proposed tailings pond brought out the suitability of the site, even when the toxic elements percolates through the subsurface formations in to the groundwater system, the existence of dykes on either side of the proposed ponding area won’t allow the water to move across them thus by restricting the contamination within the tailings pond area. Similarly, the delineation of a fault zone within the tailings pond area helped in shifting the proposed dam axis of the pond to avoid leakage through the fault zone causing concern to environment pollution.

  9. 10 CFR 61.11 - General information.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61...) Plans for use of the land disposal facility for purposes other than disposal of radioactive wastes; and..., and first emplacement of waste at the proposed land disposal facility. ...

  10. 10 CFR 61.11 - General information.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61...) Plans for use of the land disposal facility for purposes other than disposal of radioactive wastes; and..., and first emplacement of waste at the proposed land disposal facility. ...

  11. 10 CFR 61.11 - General information.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61...) Plans for use of the land disposal facility for purposes other than disposal of radioactive wastes; and..., and first emplacement of waste at the proposed land disposal facility. ...

  12. 10 CFR 61.11 - General information.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61...) Plans for use of the land disposal facility for purposes other than disposal of radioactive wastes; and..., and first emplacement of waste at the proposed land disposal facility. ...

  13. 10 CFR 61.11 - General information.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61...) Plans for use of the land disposal facility for purposes other than disposal of radioactive wastes; and..., and first emplacement of waste at the proposed land disposal facility. ...

  14. Microbial Life in the Deep Subsurface: Deep, Hot and Radioactive

    NASA Technical Reports Server (NTRS)

    DeStefano, Andrea L.; Ford, Jill C.; Winsor, Seana K.; Allen, Carlton C.; Miller, Judith; McNamara, Karen M.; Gibson, Everett K., Jr.

    2000-01-01

    Recent studies, motivated in part by the search for extraterrestrial life, continue to expand the recognized limits of Earth's biosphere. This work explored evidence for life a high-temperature, radioactive environment in the deep subsurface.

  15. High-level radioactive waste management alternatives

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

    None

    1974-05-01

    A summary of a comprehensive overview study of potential alternatives for long-term management of high-level radioactive waste is presented. The concepts studied included disposal in geologic formations, disposal in seabeds, disposal in ice caps, disposal into space, and elimination by transmutation. (TFD)

  16. 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

  17. Radioactive waste management in a hospital.

    PubMed

    Khan, Shoukat; Syed, At; Ahmad, Reyaz; Rather, Tanveer A; Ajaz, M; Jan, Fa

    2010-01-01

    Most of the tertiary care hospitals use radioisotopes for diagnostic and therapeutic applications. Safe disposal of the radioactive waste is a vital component of the overall management of the hospital waste. An important objective in radioactive waste management is to ensure that the radiation exposure to an individual (Public, Radiation worker, Patient) and the environment does not exceed the prescribed safe limits. Disposal of Radioactive waste in public domain is undertaken in accordance with the Atomic Energy (Safe disposal of radioactive waste) rules of 1987 promulgated by the Indian Central Government Atomic Energy Act 1962. Any prospective plan of a hospital that intends using radioisotopes for diagnostic and therapeutic procedures needs to have sufficient infrastructural and manpower resources to keep its ambient radiation levels within specified safe limits. Regular monitoring of hospital area and radiation workers is mandatory to assess the quality of radiation safety. Records should be maintained to identify the quality and quantity of radioactive waste generated and the mode of its disposal. Radiation Safety officer plays a key role in the waste disposal operations.

  18. Operational Strategies for Low-Level Radioactive Waste Disposal Site in Egypt - 13513

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

    Mohamed, Yasser T.

    The ultimate aims of treatment and conditioning is to prepare waste for disposal by ensuring that the waste will meet the waste acceptance criteria of a disposal facility. Hence the purpose of low-level waste disposal is to isolate the waste from both people and the environment. The radioactive particles in low-level waste emit the same types of radiation that everyone receives from nature. Most low-level waste fades away to natural background levels of radioactivity in months or years. Virtually all of it diminishes to natural levels in less than 300 years. In Egypt, The Hot Laboratories and Waste Management Centermore » has been established since 1983, as a waste management facility for LLW and ILW and the disposal site licensed for preoperational in 2005. The site accepts the low level waste generated on site and off site and unwanted radioactive sealed sources with half-life less than 30 years for disposal and all types of sources for interim storage prior to the final disposal. Operational requirements at the low-level (LLRW) disposal site are listed in the National Center for Nuclear Safety and Radiation Control NCNSRC guidelines. Additional procedures are listed in the Low-Level Radioactive Waste Disposal Facility Standards Manual. The following describes the current operations at the LLRW disposal site. (authors)« less

  19. An industry perspective on commercial radioactive waste disposal conditions and trends.

    PubMed

    Romano, Stephen A

    2006-11-01

    The United States is presently served by Class-A, -B and -C low-level radioactive waste and naturally-occurring and accelerator-produced radioactive material disposal sites in Washington and South Carolina; a Class-A and mixed waste disposal site in Utah that also accepts naturally-occurring radioactive material; and hazardous and solid waste facilities and uranium mill tailings sites that accept certain radioactive materials on a site-specific basis. The Washington site only accepts low-level radioactive waste from 11 western states due to interstate Compact restrictions on waste importation. The South Carolina site will be subject to geographic service area restrictions beginning 1 July 2008, after which only three states will have continued access. The Utah site dominates the commercial Class-A and mixed waste disposal market due to generally lower state fees than apply in South Carolina. To expand existing commercial services, an existing hazardous waste site in western Texas is seeking a Class-A, -B and -C and mixed waste disposal license. With that exception, no new Compact facilities are proposed. This fluid, uncertain situation has inspired national level rulemaking initiatives and policy studies, as well as alternative disposal practices for certain low-activity materials.

  20. Composite analysis E-area vaults and saltstone disposal facilities

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

    Cook, J.R.

    1997-09-01

    This report documents the Composite Analysis (CA) performed on the two active Savannah River Site (SRS) low-level radioactive waste (LLW) disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults (EAV) Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of SRS and contains all of the waste disposal facilities, chemical separations facilities and associated high-level waste storage facilities as well as numerous other sources of radioactive material. The analysis considered 114 potentialmore » sources of radioactive material containing 115 radionuclides. The results of the CA clearly indicate that continued disposal of low-level waste in the saltstone and EAV facilities, consistent with their respective radiological performance assessments, will have no adverse impact on future members of the public.« less

  1. 237Np analytical method using 239Np tracers and application to a contaminated nuclear disposal facility

    DOE PAGES

    Snow, Mathew S.; Morrison, Samuel S.; Clark, Sue B.; ...

    2017-03-21

    In this study, environmental 237Np analyses are challenged by low 237Np concentrations and lack of an available yield tracer; we report a rapid, inexpensive 237Np analytical approach employing the short lived 239Np (t1/2 = 2.3 days) as a chemical yield tracer followed by 237Np quantification using inductively coupled plasma-mass spectrometry. 239Np tracer is obtained via separation from a 243Am stock solution and standardized using gamma spectrometry immediately prior to sample processing. Rapid digestions using a commercial, 900 W "Walmart" microwave and Parr microwave vessels result in 99.8 ± 0.1% digestion yields, while chromatographic separations enable Np/U separation factors on themore » order of 10 6 and total Np yields of 95 ± 4% (2σ). Application of this method to legacy soil samples surrounding a radioactive disposal facility (the Subsurface Disposal Area at Idaho National Laboratory) reveal the presence of low level 237Np contamination within 600 m of this site, with maximum 237Np concentrations on the order of 10 3 times greater than nuclear weapons testing fallout levels.« less

  2. 237 Np analytical method using 239 Np tracers and application to a contaminated nuclear disposal facility

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

    Snow, Mathew S.; Morrison, Samuel S.; Clark, Sue B.

    2017-06-01

    Environmental 237Np analyses are challenged by low 237Np concentrations and lack of an available yield tracer; we report a rapid, inexpensive 237Np analytical approach employing the short lived 239Np (t1/2 = 2.3 days) as a chemical yield tracer followed by 237Np quantification using inductively coupled plasma-mass spectrometry. 239Np tracer is obtained via separation from a 243Am stock solution and standardized using gamma spectrometry immediately prior to sample processing. Rapid digestions using a commercial, 900 watt “Walmart” microwave and Parr microwave vessels result in 99.8 ± 0.1% digestion yields, while chromatographic separations enable Np/U separation factors on the order of 106more » and total Np yields of 95 ± 4% (2σ). Application of this method to legacy soil samples surrounding a radioactive disposal facility (the Subsurface Disposal Area at Idaho National Laboratory) reveal the presence of low level 237Np contamination within 600 meters of this site, with maximum 237Np concentrations on the order of 103 times greater than nuclear weapons testing fallout levels.« less

  3. 237Np analytical method using 239Np tracers and application to a contaminated nuclear disposal facility.

    PubMed

    Snow, Mathew S; Morrison, Samuel S; Clark, Sue B; Olson, John E; Watrous, Matthew G

    2017-06-01

    Environmental 237 Np analyses are challenged by low 237 Np concentrations and lack of an available yield tracer; we report a rapid, inexpensive 237 Np analytical approach employing the short lived 239 Np (t 1/2  = 2.3 days) as a chemical yield tracer followed by 237 Np quantification using inductively coupled plasma-mass spectrometry. 239 Np tracer is obtained via separation from a 243 Am stock solution and standardized using gamma spectrometry immediately prior to sample processing. Rapid digestions using a commercial, 900 W "Walmart" microwave and Parr microwave vessels result in 99.8 ± 0.1% digestion yields, while chromatographic separations enable Np/U separation factors on the order of 10 6 and total Np yields of 95 ± 4% (2σ). Application of this method to legacy soil samples surrounding a radioactive disposal facility (the Subsurface Disposal Area at Idaho National Laboratory) reveal the presence of low level 237 Np contamination within 600 m of this site, with maximum 237 Np concentrations on the order of 10 3 times greater than nuclear weapons testing fallout levels. Copyright © 2017 Elsevier Ltd. All rights reserved.

  4. The safe disposal of radioactive wastes

    PubMed Central

    Kenny, A. W.

    1956-01-01

    A comprehensive review is given of the principles and problems involved in the safe disposal of radioactive wastes. The first part is devoted to a study of the basic facts of radioactivity and of nuclear fission, the characteristics of radioisotopes, the effects of ionizing radiations, and the maximum permissible levels of radioactivity for workers and for the general public. In the second part, the author describes the different types of radioactive waste—reactor wastes and wastes arising from the use of radioisotopes in hospitals and in industry—and discusses the application of the maximum permissible levels of radioactivity to their disposal and treatment, illustrating his discussion with an account of the methods practised at the principal atomic energy establishments. PMID:13374534

  5. Status of the waste assay for nonradioactive disposal (WAND) project

    NASA Astrophysics Data System (ADS)

    Arnone, Gaetano L.; Foster, Lynn A.; Foxx, Charles L.; Hagan, Roland C.; Martin, E. R.; Myers, Steven C.; Parker, Jack L.

    1999-01-01

    The WAND (Waste Assay for Nonradioactive Disposal) system scans thought-to-be-clean, low-density waste (mostly paper and plastics) to verify the absence of radioactive contaminants at very low-levels. Much of the low-density waste generated in radiologically controlled areas, formally considered `suspect' radioactive, is now disposed more cheaply at the Los Alamos County Landfill as opposed to the LANL Radioactive Waste Landfill.

  6. Radioactive Waste Management in A Hospital

    PubMed Central

    Khan, Shoukat; Syed, AT; Ahmad, Reyaz; Rather, Tanveer A.; Ajaz, M; Jan, FA

    2010-01-01

    Most of the tertiary care hospitals use radioisotopes for diagnostic and therapeutic applications. Safe disposal of the radioactive waste is a vital component of the overall management of the hospital waste. An important objective in radioactive waste management is to ensure that the radiation exposure to an individual (Public, Radiation worker, Patient) and the environment does not exceed the prescribed safe limits. Disposal of Radioactive waste in public domain is undertaken in accordance with the Atomic Energy (Safe disposal of radioactive waste) rules of 1987 promulgated by the Indian Central Government Atomic Energy Act 1962. Any prospective plan of a hospital that intends using radioisotopes for diagnostic and therapeutic procedures needs to have sufficient infrastructural and manpower resources to keep its ambient radiation levels within specified safe limits. Regular monitoring of hospital area and radiation workers is mandatory to assess the quality of radiation safety. Records should be maintained to identify the quality and quantity of radioactive waste generated and the mode of its disposal. Radiation Safety officer plays a key role in the waste disposal operations. PMID:21475524

  7. [Investigation of actual condition of management and disposal of medical radioactive waste in Korea].

    PubMed

    Watanabe, Hiroshi; Nagaoka, Hiroaki; Yamaguchi, Ichiro; Horiuchi, Shoji; Imoto, Atsushi

    2009-07-20

    In order to realize the rational management and disposal of radioactive waste like DIS or its clearance as performed in Europe, North America, and Japan, we investigated the situation of medical radioactive waste in Korea and its enforcement. We visited three major Korean facilities in May 2008 and confirmed details of the procedure being used by administering a questionnaire after our visit. From the results, we were able to verify that the governmental agency had established regulations for the clearance of radioactive waste as self-disposal based on the clearance level of IAEA in Korea and that the medical facilities performed suitable management and disposal of radioactive waste based on the regulations and superintendence of a radiation safety officer. The type of nuclear medicine was almost the same as that in Japan, and the half-life of all radiopharmaceuticals was 60 days or less. While performing regulatory adjustment concerning the rational management and disposal of radioactive waste in Korea for reference also in this country, it is important to provide an enforcement procedure with quality assurance in the regulations.

  8. 10 CFR 62.13 - Contents of a request for emergency access: Alternatives.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... radioactive waste in a licensed storage facility; (3) Obtaining access to a disposal facility by voluntary... disposal at a Federal low-level radioactive waste disposal facility in the case of a Federal or defense... EMERGENCY ACCESS TO NON-FEDERAL AND REGIONAL LOW-LEVEL WASTE DISPOSAL FACILITIES Request for a Commission...

  9. Drilling effect on subsurface microbial community structure in groundwater from the -250 m gallery at the Horonobe Underground Research Laboratory, Japan

    NASA Astrophysics Data System (ADS)

    Ise, K.; Amano, Y.; Sasaki, Y.; Yoshikawa, H.

    2014-12-01

    The deep geological disposal system is regarded as the most secure and practical disposal method of high-level radioactive waste in the world. In this disposal system, preservation of reducing condition is one of the key requirements, because most of radionuclides have low solubilities in such condition. However, the host rocks near the shafts and galleries would be affected by oxidization during the construction and operation period of a repository (for about 50 years). Therefore, the recovery of reducing condition after closing the repository should be verified. During the recovery processes, it is considered that microbial activities play important roles, but the mechanisms are poorly understood. In this study, we monitored the changes in microbial communities by molecular method to evaluate microbial response toward the oxygen stress. The groundwater samples were collected from a borehole of 250 m depth at the Horonobe Underground Research Laboratory, for two years immediately after drilling of a borehole without any contamination as much as possible. Immediately after drilling of the borehole, the phylotype related to Arcobacter spp. was dominated about 65 % of the total clone library. Arcobacter spp. is known as sulfide oxidizer and which can growth chemoautotrophically. Half a year later, the phylotype related to Azoarcus spp. and Pseudomonas spp. known as nitrate reducing bacteria increased, instead of the phylotype related to Arcobacter spp. One year later, in addition to nitrate reducing bacteria, phylotype related to Dethiobacterspp. known as thiosulfate reducing bacteria was dominantly detected. Two years later, most of detected clones were related to uncultured species such as candidate division WS6 and JS1 which are detected frequently in deep-sea sediments. Our results indicate that these redox sequential reactions could contribute to the recovery and maintenance of reducing conditions and provide a conceptual model for evaluating the capacity to recover reducing conditions in subsurface environments after final geological disposal and the post-closure.

  10. Management of low-level radioactive waste in Israel

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

    Shabtai, B.; Brenner, S.; Ne`eman, E.

    1995-12-31

    Radioactive materials are used extensively in Israel in many areas and applications for medicine, industry, agriculture, research and development and others. Israel`s primary concern in waste management is population safety and environmental protection. The Ministry of The Environment (MOE), in cooperation with the Israeli Atomic Energy Commission (IAEC), supervise over the disposal system, and ensure an effective control. The MOE is responsible for the granting of permits to users of radioactive elements in about 300 plants and institutes, with about 2,200 installations. The MOE operates a computerized database management system (DBMS) on radioactive materials, with data on licensing, import andmore » distribution, waste disposal and transportation. Supervision over the disposal of LLRW has deepened recently, and periodic reports, based on the number of drums containing LLRW, which were transferred from all institutes in Israel to the NRWDS, were prepared. Draft regulations on the disposal of LLRW from institutes of research and education, hospitals, medical laboratories and other, have been recently prepared. These regulations include instructions on the disposal of solid and liquid LLRW as well as radioactive gases and vapors. As a general rule, no LLRW of any sort will be disposed of through the ordinary waste system or general sewage. However, in some extraordinary cases, residues of liquid LLRW are allowed to be disposed in this manner, if the requirements for disposal are satisfied. There are some conditions, in which solid LLRW might be treated as a conventional waste, as well as for safe emission of radioactive gases and aerosols. In light of these considerations, a new and more specific approach to radiation protection organizations and management of low-level radioactive waste problems, supervision and optimization is presented.« less

  11. Safety assessment of borehole disposal of unwanted radioactive sealed sources in Egypt using Goldsim.

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

    Cochran, John Russell; Mattie, Patrick D.

    2004-10-01

    A radioactive sealed source is any radioactive material that is encased in a capsule designed to prevent leakage or escape of the radioactive material. Radioactive sealed sources are used for a wide variety of applications at hospitals, in manufacturing and research. Typical uses are in portable gauges to measure soil compaction and moisture or to determine physical properties of rocks units in boreholes (well logging). Hospitals and clinics use radioactive sealed sources for teletherapy and brachytherapy. Oil exploration and medicine are the largest users. Accidental mismanagement of radioactive sealed sources each year results in a large number of people receivingmore » very high or even fatal does of ionizing radiation. Deliberate mismanagement is a growing international concern. Sealed sources must be managed and disposed effectively in order to protect human health and the environment. Effective national safety and management infrastructures are prerequisites for efficient and safe transportation, treatment, storage, and disposal. The Integrated Management Program for Radioactive Sealed Sources in Egypt (IMPRSS) is a cooperative development agreement between the Egyptian Atomic Energy Authority (EAEA), Egyptian Ministry of Health (MOH), Sandia National Laboratories (SNL), the University of New Mexico (UNM), and Agriculture Cooperative Development International (ACDI/VOCA). The EAEA, teaming with SNL, is conducting a Preliminary Safety Assessment (PSA) of an intermediate-depth borehole disposal in thick arid alluvium in Egypt based on experience with the U.S. Greater Confinement Disposal (GCD). Goldsim has been selected for the preliminary disposal system assessment for the Egyptian GCD Study. The results of the PSA will then be used to decide if Egypt desires to implement such a disposal system.« less

  12. Microbial reduction of U(VI) under alkaline conditions: implications for radioactive waste geodisposal.

    PubMed

    Williamson, Adam J; Morris, Katherine; Law, Gareth T W; Rizoulis, Athanasios; Charnock, John M; Lloyd, Jonathan R

    2014-11-18

    Although there is consensus that microorganisms significantly influence uranium speciation and mobility in the subsurface under circumneutral conditions, microbiologically mediated U(VI) redox cycling under alkaline conditions relevant to the geological disposal of cementitious intermediate level radioactive waste, remains unexplored. Here, we describe microcosm experiments that investigate the biogeochemical fate of U(VI) at pH 10-10.5, using sediments from a legacy lime working site, stimulated with an added electron donor, and incubated in the presence and absence of added Fe(III) as ferrihydrite. In systems without added Fe(III), partial U(VI) reduction occurred, forming a U(IV)-bearing non-uraninite phase which underwent reoxidation in the presence of air (O2) and to some extent nitrate. By contrast, in the presence of added Fe(III), U(VI) was first removed from solution by sorption to the Fe(III) mineral, followed by bioreduction and (bio)magnetite formation coupled to formation of a complex U(IV)-bearing phase with uraninite present, which also underwent air (O2) and partial nitrate reoxidation. 16S rRNA gene pyrosequencing showed that Gram-positive bacteria affiliated with the Firmicutes and Bacteroidetes dominated in the post-reduction sediments. These data provide the first insights into uranium biogeochemistry at high pH and have significant implications for the long-term fate of uranium in geological disposal in both engineered barrier systems and the alkaline, chemically disturbed geosphere.

  13. [Cobalt(III)-EDTA] - Reduction by Thermophilic Methanogen Methanothermobacter Thermautotrophicus

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

    Singh, Rajesh; Dong, Hailiang; Liu, Deng

    2015-06-30

    Cobalt is a metal contaminant at high temperature radioactive waste disposal sites. In previous studies have largely focused on mesophilic microorganisms to remediate cobalt, despite the presence of thermophilic microorganisms at such sites. In this study,Methanothermobacter thermautotrophicus, a thermophilic methanogen, was used to reduce Co(III) in the form of [Co(III)–EDTA] -. Bioreduction experiments were conducted in a growth medium with H 2/CO 2 as a growth substrate at initial Co(III) concentrations of 1, 2, 4, 7, and 10 mM. At low Co(III) concentrations (< 4 mM), a complete reduction was observed within a week. Wet chemistry, X-ray absorption near-edge structuremore » (XANES) and electron paramagnetic resonance (EPR) analyses were all consistent in revealing the reduction kinetics. But, at higher concentrations (7 and 10 mM) the reduction extents only reached 69.8% and 48.5%, respectively, likely due to the toxic effect of Co(III) to the methanogen cells as evidenced by a decrease in total cellular protein at these Co(III) concentrations. Methanogenesis was inhibited by Co(III) bioreduction, possibly due to impaired cell growth and electron diversion from CO 2 to Co(III). Overall, our results demonstrated the ability of M. thermautotrophicus to reduce Co(III) to Co(II) and its potential application for remediating 60Co contaminant at high temperature subsurface radioactive waste disposal sites.« less

  14. Radioactive waste disposal in the marine environment

    NASA Astrophysics Data System (ADS)

    Anderson, D. R.

    In order to find the optimal solution to waste disposal problems, it is necessary to make comparisons between disposal media. It has become obvious to many within the scientific community that the single medium approach leads to over protection of one medium at the expense of the others. Cross media comparisons are being conducted in the Department of Energy ocean disposal programs for several radioactive wastes. Investigations in three areas address model development, comparisons of laboratory tests with field results and predictions, and research needs in marine disposal of radioactive waste. Tabulated data are included on composition of liquid high level waste and concentration of some natural radionuclides in the sea.

  15. Radioactive waste disposal fees-Methodology for calculation

    NASA Astrophysics Data System (ADS)

    Bemš, Július; Králík, Tomáš; Kubančák, Ján; Vašíček, Jiří; Starý, Oldřich

    2014-11-01

    This paper summarizes the methodological approach used for calculation of fee for low- and intermediate-level radioactive waste disposal and for spent fuel disposal. The methodology itself is based on simulation of cash flows related to the operation of system for waste disposal. The paper includes demonstration of methodology application on the conditions of the Czech Republic.

  16. 10 CFR 61.3 - License required.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.3 License required. (a) No person may receive, possess, and dispose of radioactive waste containing source, special nuclear, or byproduct material at a land disposal facility unless authorized by a...

  17. 10 CFR 61.59 - Institutional requirements.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.59 Institutional requirements. (a) Land ownership. Disposal of radioactive waste received from other persons may be permitted only on land owned in fee by the...

  18. 10 CFR 61.3 - License required.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.3 License required. (a) No person may receive, possess, and dispose of radioactive waste containing source, special nuclear, or byproduct material at a land disposal facility unless authorized by a...

  19. 10 CFR 61.59 - Institutional requirements.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.59 Institutional requirements. (a) Land ownership. Disposal of radioactive waste received from other persons may be permitted only on land owned in fee by the...

  20. 10 CFR 61.3 - License required.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.3 License required. (a) No person may receive, possess, and dispose of radioactive waste containing source, special nuclear, or byproduct material at a land disposal facility unless authorized by a...

  1. 10 CFR 61.3 - License required.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.3 License required. (a) No person may receive, possess, and dispose of radioactive waste containing source, special nuclear, or byproduct material at a land disposal facility unless authorized by a...

  2. 10 CFR 61.3 - License required.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.3 License required. (a) No person may receive, possess, and dispose of radioactive waste containing source, special nuclear, or byproduct material at a land disposal facility unless authorized by a...

  3. 10 CFR 61.59 - Institutional requirements.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.59 Institutional requirements. (a) Land ownership. Disposal of radioactive waste received from other persons may be permitted only on land owned in fee by the...

  4. 10 CFR 61.59 - Institutional requirements.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.59 Institutional requirements. (a) Land ownership. Disposal of radioactive waste received from other persons may be permitted only on land owned in fee by the...

  5. 10 CFR 61.59 - Institutional requirements.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.59 Institutional requirements. (a) Land ownership. Disposal of radioactive waste received from other persons may be permitted only on land owned in fee by the...

  6. Radioactive Waste Characterization Strategies; Comparisons Between AK/PK, Dose to Curie Modeling, Gamma Spectroscopy, and Laboratory Analysis Methods- 12194

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

    Singledecker, Steven J.; Jones, Scotty W.; Dorries, Alison M.

    2012-07-01

    In the coming fiscal years of potentially declining budgets, Department of Energy facilities such as the Los Alamos National Laboratory (LANL) will be looking to reduce the cost of radioactive waste characterization, management, and disposal processes. At the core of this cost reduction process will be choosing the most cost effective, efficient, and accurate methods of radioactive waste characterization. Central to every radioactive waste management program is an effective and accurate waste characterization program. Choosing between methods can determine what is classified as low level radioactive waste (LLRW), transuranic waste (TRU), waste that can be disposed of under an Authorizedmore » Release Limit (ARL), industrial waste, and waste that can be disposed of in municipal landfills. The cost benefits of an accurate radioactive waste characterization program cannot be overstated. In addition, inaccurate radioactive waste characterization of radioactive waste can result in the incorrect classification of radioactive waste leading to higher disposal costs, Department of Transportation (DOT) violations, Notice of Violations (NOVs) from Federal and State regulatory agencies, waste rejection from disposal facilities, loss of operational capabilities, and loss of disposal options. Any one of these events could result in the program that mischaracterized the waste losing its ability to perform it primary operational mission. Generators that produce radioactive waste have four characterization strategies at their disposal: - Acceptable Knowledge/Process Knowledge (AK/PK); - Indirect characterization using a software application or other dose to curie methodologies; - Non-Destructive Analysis (NDA) tools such as gamma spectroscopy; - Direct sampling (e.g. grab samples or Surface Contaminated Object smears) and laboratory analytical; Each method has specific advantages and disadvantages. This paper will evaluate each method detailing those advantages and disadvantages including; - Cost benefit analysis (basic materials costs, overall program operations costs, man-hours per sample analyzed, etc.); - Radiation Exposure As Low As Reasonably Achievable (ALARA) program considerations; - Industrial Health and Safety risks; - Overall Analytical Confidence Level. The concepts in this paper apply to any organization with significant radioactive waste characterization and management activities working to within budget constraints and seeking to optimize their waste characterization strategies while reducing analytical costs. (authors)« less

  7. Chlorine-36 in the Snake River Plain Aquifer at the Idaho National Engineering Laboratory; origin and implications

    USGS Publications Warehouse

    Beasley, T.M.; Cecil, L.D.; Sharma, P.; Kubik, P.W.; Fehn, U.; Mann, L.J.; Gove, H.E.

    1993-01-01

    Between 1952 and 1984, low-level radioactive waste was introduced directly into the Snake River Plain aquifer at the Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho. These wastes were generated, principally, at the nuclear fuel reprocessing facility on the site. Our measurements of 36C1 in monitoring and production well waters, downgradient from disposal wells and seepage ponds, found easily detectable, nonhazardous concentrations of this radionuclide from the point of injection to the INEL southern site boundary. Comparisons are made between 3H and 36Cl concentrations in aquifer water and the advantages of 36C1 as a tracer of subsurface-water dynamics at the site are discussed.

  8. Gamma-ray spectrometry method used for radioactive waste drums characterization for final disposal at National Repository for Low and Intermediate Radioactive Waste--Baita, Romania.

    PubMed

    Done, L; Tugulan, L C; Dragolici, F; Alexandru, C

    2014-05-01

    The Radioactive Waste Management Department from IFIN-HH, Bucharest, performs the conditioning of the institutional radioactive waste in concrete matrix, in 200 l drums with concrete shield, for final disposal at DNDR - Baita, Bihor county, in an old exhausted uranium mine. This paper presents a gamma-ray spectrometry method for the characterization of the radioactive waste drums' radionuclides content, for final disposal. In order to study the accuracy of the method, a similar concrete matrix with Portland cement in a 200 l drum was used. © 2013 The Authors. Published by Elsevier Ltd All rights reserved.

  9. 10 CFR 62.11 - Filing and distribution of a determination request.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... radioactive waste disposal facilities, to the Compact Commissions with operating regional low-level radioactive waste disposal facilities, and to the Governors of the States in the Compact Commissions with... ACCESS TO NON-FEDERAL AND REGIONAL LOW-LEVEL WASTE DISPOSAL FACILITIES Request for a Commission...

  10. 10 CFR 61.20 - Filing and distribution of application.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... license covering the receipt and disposal of radioactive wastes in a land disposal facility are required....20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.20 Filing and distribution of application. (a) An application for a license...

  11. 10 CFR 61.20 - Filing and distribution of application.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... license covering the receipt and disposal of radioactive wastes in a land disposal facility are required....20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.20 Filing and distribution of application. (a) An application for a license...

  12. 10 CFR 61.20 - Filing and distribution of application.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... license covering the receipt and disposal of radioactive wastes in a land disposal facility are required....20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.20 Filing and distribution of application. (a) An application for a license...

  13. 10 CFR 61.20 - Filing and distribution of application.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... license covering the receipt and disposal of radioactive wastes in a land disposal facility are required....20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.20 Filing and distribution of application. (a) An application for a license...

  14. 10 CFR 61.20 - Filing and distribution of application.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... license covering the receipt and disposal of radioactive wastes in a land disposal facility are required....20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.20 Filing and distribution of application. (a) An application for a license...

  15. International Collaboration Activities on Engineered Barrier Systems

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

    Jove-Colon, Carlos F.

    The Used Fuel Disposition Campaign (UFDC) within the DOE Fuel Cycle Technologies (FCT) program has been engaging in international collaborations between repository R&D programs for high-level waste (HLW) disposal to leverage on gathered knowledge and laboratory/field data of near- and far-field processes from experiments at underground research laboratories (URL). Heater test experiments at URLs provide a unique opportunity to mimetically study the thermal effects of heat-generating nuclear waste in subsurface repository environments. Various configurations of these experiments have been carried out at various URLs according to the disposal design concepts of the hosting country repository program. The FEBEX (Full-scale Engineeredmore » Barrier Experiment in Crystalline Host Rock) project is a large-scale heater test experiment originated by the Spanish radioactive waste management agency (Empresa Nacional de Residuos Radiactivos S.A. – ENRESA) at the Grimsel Test Site (GTS) URL in Switzerland. The project was subsequently managed by CIEMAT. FEBEX-DP is a concerted effort of various international partners working on the evaluation of sensor data and characterization of samples obtained during the course of this field test and subsequent dismantling. The main purpose of these field-scale experiments is to evaluate feasibility for creation of an engineered barrier system (EBS) with a horizontal configuration according to the Spanish concept of deep geological disposal of high-level radioactive waste in crystalline rock. Another key aspect of this project is to improve the knowledge of coupled processes such as thermal-hydro-mechanical (THM) and thermal-hydro-chemical (THC) operating in the near-field environment. The focus of these is on model development and validation of predictions through model implementation in computational tools to simulate coupled THM and THC processes.« less

  16. Hydrogeological Characteristics of Fractured Rocks around the In-DEBS Test Borehole at the Underground Research Facility (KURT)

    NASA Astrophysics Data System (ADS)

    Ko, Nak-Youl; Kim, Geon Young; Kim, Kyung-Su

    2016-04-01

    In the concept of the deep geological disposal of radioactive wastes, canisters including high-level wastes are surrounded by engineered barrier, mainly composed of bentonite, and emplaced in disposal holes drilled in deep intact rocks. The heat from the high-level radioactive wastes and groundwater inflow can influence on the robustness of the canister and engineered barrier, and will be possible to fail the canister. Therefore, thermal-hydrological-mechanical (T-H-M) modeling for the condition of the disposal holes is necessary to secure the safety of the deep geological disposal. In order to understand the T-H-M coupling phenomena at the subsurface field condition, "In-DEBS (In-Situ Demonstration of Engineered Barrier System)" has been designed and implemented in the underground research facility, KURT (KAERI Underground Research Tunnel) in Korea. For selecting a suitable position of In-DEBS test and obtaining hydrological data to be used in T-H-M modeling as well as groundwater flow simulation around the test site, the fractured rock aquifer including the research modules of KURT was investigated through the in-situ tests at six boreholes. From the measured data and results of hydraulic tests, the range of hydraulic conductivity of each interval in the boreholes is about 10-7-10-8 m/s and that of influx is about 10-4-10-1 L/min for NX boreholes, which is expected to be equal to about 0.1-40 L/min for the In-DEBS test borehole (diameter of 860 mm). The test position was determined by the data and availability of some equipment for installing In-DEBS in the test borehole. The mapping for the wall of test borehole and the measurements of groundwater influx at the leaking locations was carried out. These hydrological data in the test site will be used as input of the T-H-M modeling for simulating In-DEBS test.

  17. 10 CFR 62.1 - Purpose and scope.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... (42 U.S.C. 2021) to any non-Federal or regional low-level radioactive waste (LLW) disposal facility or... regional or non-Federal low-level radioactive waste disposal facilities and who submit a request to the... LOW-LEVEL WASTE DISPOSAL FACILITIES General Provisions § 62.1 Purpose and scope. (a) The regulations...

  18. 10 CFR 961.1 - Purpose.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... STANDARD CONTRACT FOR DISPOSAL OF SPENT NUCLEAR FUEL AND/OR HIGH-LEVEL RADIOACTIVE WASTE General § 961.1... fuel (SNF) and high-level radioactive waste (HLW) as provided in section 302 of the Nuclear Waste... title to, transport, and dispose of spent nuclear fuel and/or high-level radioactive waste delivered to...

  19. 10 CFR 35.92 - Decay-in-storage.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... days for decay-in-storage before disposal without regard to its radioactivity if it— (1) Monitors byproduct material at the surface before disposal and determines that its radioactivity cannot be...

  20. Viral Tracer Studies Indicate Contamination of Marine Waters by Sewage Disposal Practices in Key Largo, Florida

    PubMed Central

    Paul, J. H.; Rose, J. B.; Brown, J.; Shinn, E. A.; Miller, S.; Farrah, S. R.

    1995-01-01

    Domestic wastewater disposal practices in the Florida Keys are primarily limited to on-site disposal systems such as septic tanks, injection wells, and illegal cesspits. Poorly treated sewage is thus released into the highly porous subsurface Key Largo limestone matrix. To investigate the fate and transport of sewage in the subsurface environment and the potential for contamination of marine surface waters, we employed bacteriophages as tracers in a domestic septic system and a simulated injection well in Key Largo, Florida. Transport of bacteriophage (Phi)HSIC-1 from the septic tank to adjacent surface canal waters and outstanding marine waters occurred in as little as 11 and 23 h, respectively. Transport of the Salmonella phage PRD1 from the simulated injection well to a canal adjacent to the injection site occurred in 11.2 h. Estimated rates of migration of viral tracers ranged from 0.57 to 24.2 m/h, over 500-fold greater than flow rates measured previously by subsurface flow meters in similar environments. These results suggest that current on-site disposal practices can lead to contamination of the subsurface and surface marine waters in the Keys. PMID:16535046

  1. Viral tracer studies indicate contamination of marine waters by sewage disposal practices in key largo, Florida.

    PubMed

    Paul, J H; Rose, J B; Brown, J; Shinn, E A; Miller, S; Farrah, S R

    1995-06-01

    Domestic wastewater disposal practices in the Florida Keys are primarily limited to on-site disposal systems such as septic tanks, injection wells, and illegal cesspits. Poorly treated sewage is thus released into the highly porous subsurface Key Largo limestone matrix. To investigate the fate and transport of sewage in the subsurface environment and the potential for contamination of marine surface waters, we employed bacteriophages as tracers in a domestic septic system and a simulated injection well in Key Largo, Florida. Transport of bacteriophage (Phi)HSIC-1 from the septic tank to adjacent surface canal waters and outstanding marine waters occurred in as little as 11 and 23 h, respectively. Transport of the Salmonella phage PRD1 from the simulated injection well to a canal adjacent to the injection site occurred in 11.2 h. Estimated rates of migration of viral tracers ranged from 0.57 to 24.2 m/h, over 500-fold greater than flow rates measured previously by subsurface flow meters in similar environments. These results suggest that current on-site disposal practices can lead to contamination of the subsurface and surface marine waters in the Keys.

  2. Borehole Disposal and the Cradle-To-Grave Management Program for Radioactive Sealed Sources in Egypt

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

    Cochran, J.R.; Carson, S.D.; El-Adham, K.

    2006-07-01

    The Integrated Management Program for Radioactive Sealed Sources (IMPRSS) is greatly improving the management of radioactive sealed sources (RSSs) in Egypt. When completed, IMPRSS will protect the people and the environment from another radioactive incident. The Government of Egypt and Sandia National Laboratories are collaboratively implementing IMPRSS. The integrated activities are divided into three broad areas: the safe management of RSSs in-use, the safe management of unwanted RSSs, and crosscutting infrastructure. Taken together, these work elements comprise a cradle-to-grave program. To ensure sustainability, the IMPRSS emphasizes such activities as human capacity development through technology transfer and training, and development ofmore » a disposal facility. As a key step in the development of a disposal facility, IMPRSS is conducting a safety assessment for intermediate-depth borehole disposal in thick arid alluvium in Egypt based on experience with the U.S.'s Greater Confinement Disposal boreholes. This safety assessment of borehole disposal is being supported by the International Atomic Energy Agency (IAEA) through an IAEA Technical Cooperation Project. (authors)« less

  3. 75 FR 15423 - U.S. Nuclear Regulatory Commission Technical Evaluation Report for the Phase 1 Decommissioning...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-29

    ... DOE to carry out a high-level radioactive waste management demonstration project at the Western New... solidification of high-level radioactive waste for disposal in a Federal repository for permanent disposal. The... and other facilities where the solidified high-level radioactive waste was stored, the facilities used...

  4. Classification of the Inventory of Spent Sealed Sources at INSHAS Storage Facility

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

    El-Adham, K.; Geleel, M.A.; Mahmoud, N.S.

    2006-07-01

    The Egyptian Atomic Energy Authority (EAEA) is responsible for the recovery, transportation, conditioning, storage and disposal of all unwanted spent sealed radioactive sources (SSSs) in Egypt. Because of radioactive decay, damage, misuse or changing technical conditions, approximately 600 unwanted SSSs are now in storage at the EAEA's Hot-Laboratories Center in INSHAS. For the safe recovery, transportation, conditioning and storage of these unwanted SSSs the EAEA uses an International Atomic Energy Agency's (IAEA's) categorization system. The IAEA system classifies sealed radioactive sources (SRSs) into five categories based on potential risks to current workers and the public. This IAEA system allows Membermore » States like Egypt to apply a graded approach to the management of SRSs and SSSs. With over 600 unwanted SSSs already in storage, the EAEA is planned to dispose unwanted SSSs in near surface vault structures with solidified low- and intermediate-level radioactive wastes. The IAEA's categorization system is not designed to protect future populations from the possible long-term migration of radioactive wastes from a disposal system. This paper presents the basis of a second categorization system, designed to protect the public in Egypt from radioactive wastes that may migrate from a near-surface disposal facility. Assuming a release of radionuclides from the near-surface vaults 150 years after disposal and consumption of contaminated groundwater at the 150 m fence-line, this classification systems ranks SSSs into two groups: Those appropriate for near-surface disposal and those SSSs requiring greater isolation. Intermediate depth borehole disposal is proposed for those SSSs requiring greater isolation. Assistance with intermediate-depth borehole disposal is being provided by the Integrated Management Program for Radioactive Sealed Sources (IMPRSS) and by the IAEA through a Technical Cooperation Project. IMPRSS is a joint Egyptian / U.S. program that is greatly improving the cradle-to-grave management of SRSs and SSSs in Egypt. As a component of IMPRSS, Sandia National Laboratories is transferring knowledge to the Egyptian counterparts from implementation of the Greater Confinement Disposal boreholes in the U.S. (authors)« less

  5. Technical and design update in the AUBE French low-level radioactive waste disposal facility

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

    Marque, Y.

    1989-01-01

    Long-term industrial management of radioactive waste in France is carried out by the Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA). ANDRA is in charge of design, siting, construction, and operation of disposal centers. The solution selected in France for the disposal of low- and medium-level, short-lived radioactive waste is near-surface disposal in the earth using the principle of multiple barriers, in accordance with national safety rules and regulations, and based on operating experience from the Centre de Stockage de la Manche. Since the center's start-up in 1969, 400,000 m{sup 3} of waste have been disposed of. The Frenchmore » national program for waste management is proceeding with the construction of a second near-surface disposal, which is expected to be operational in 1991. It is located in the department of AUBE (from which its name derives), 100 miles southeast of Paris. The paper describes the criteria for siting and design of the AUBE disposal facility, design of the AUBE facility disposal module, and comparison with North Carolina and Pennsylvania disposal facility designs.« less

  6. Radioactive waste disposal implications of extending Part IIA of the Environmental Protection Act to cover radioactively contaminated land.

    PubMed

    Nancarrow, D J; White, M M

    2004-03-01

    A short study has been carried out of the potential radioactive waste disposal issues associated with the proposed extension of Part IIA of the Environmental Protection Act 1990 to include radioactively contaminated land, where there is no other suitable existing legislation. It was found that there is likely to be an availability problem with respect to disposal at landfills of the radioactive wastes arising from remediation. This is expected to be principally wastes of high volume and low activity (categorised as low level waste (LLW) and very low level waste (VLLW)). The availability problem results from a lack of applications by landfill operators for authorisation to accept LLW wastes for disposal. This is apparently due to perceived adverse publicity associated with the consultation process for authorisation coupled with uncertainty over future liabilities. Disposal of waste as VLLW is limited both by questions over volumes that may be acceptable and, more fundamentally, by the likely alpha activity of wastes (originating from radium and thorium operations). Authorised on-site disposal has had little attention in policy and guidance in recent years, but may have a part to play, especially if considered commercially attractive. Disposal at BNFL's near surface disposal facility for LLW at Drigg is limited to wastes for which there are no practical alternative disposal options (and preference has been given to operational type wastes). Therefore, wastes from the radioactively contaminated land (RCL) regime are not obviously attractive for disposal to Drigg. Illustrative calculations have been performed based on possible volumes and activities of RCL arisings (and assuming Drigg's future volumetric disposal capacity is 950,000 m3). These suggest that wastes arising from implementing the RCL regime, if all disposed to Drigg, would not represent a significant fraction of the volumetric capacity of Drigg, but could have a significant impact on the radiological capacity with respect to 226Ra plus 232Th. The government's decision-making programme for managing solid radioactive wastes in the UK may possibly achieve a general consensus that the use of landfill for LLW from the RCL regime has a fundamental role to play. However, this is unlikely to change the situation within the next few years. No new national facility arising from this programme is likely to be available during the first decade of the operation of a new RCL regime. Hence it appears that Drigg will need to play an important role for some years to come.

  7. Construction of a naturally occurring radioactive material project in the BeAAT hazardous waste facilities.

    PubMed

    Abuahmad, H

    2015-06-01

    This paper does not necessarily reflect the views of the International Commission on Radiological Protection. Naturally occurring radioactive material (NORM) is produced during exploration and production operations of subsidiaries of the Abu Dhabi National Oil Company (ADNOC) in the United Arab Emirates, and accumulates in drilling tubulars, plant equipment, and components. These NORM hazardous wastes need to be managed in such a way that they do not damage human health and the environment. The primary radionuclides of concern in the oil and gas industries are radium-226 and radium-228. These radioisotopes are the decay products of uranium and thorium isotopes that are present in subsurface formations from which hydrocarbons are produced. While uranium and thorium are largely immobile, radium is slightly more soluble and may become mobilised in the fluid phases of the formation (International Association of Oil & Gas Producers, 2008). In order to treat and dispose of NORM waste products safely, ADNOC's subsidiary 'TAKREER' is developing a new facility, on behalf of all ADNOC subsidiaries, within the existing Central Environmental Protection Facilities (BeAAT) in Ruwais city. The NORM plant is envisaged to treat, handle, and dispose of NORM waste in the forms of scale, sludge, and contaminated equipment. The NORM treatment facility will cover activities such as decontamination, volume reduction, NORM handling, and concrete immobilisation of NORM waste into packages for designated landfilling. © The International Society for Prosthetics and Orthotics Reprints and permissions: sagepub.co.uk/journalsPermissions.nav.

  8. 10 CFR 62.13 - Contents of a request for emergency access: Alternatives.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... EMERGENCY ACCESS TO NON-FEDERAL AND REGIONAL LOW-LEVEL WASTE DISPOSAL FACILITIES Request for a Commission... following: (1) Storage of low-level radioactive waste at the site of generation; (2) Storage of low-level... disposal at a Federal low-level radioactive waste disposal facility in the case of a Federal or defense...

  9. Landfill disposal systems.

    PubMed

    Slimak, K M

    1978-12-01

    The current status of landfill disposal of hazardous wastes in the United States is indicated by presenting descriptions of six operating landfills. These landfills illustrate the variety of techniques that exist in landfill disposal of hazardous wastes. Although some landfills more effectively isolate hazardous waste than others, all landfills must deal with the following problems. Leachate from hazardous waste landfills is generally highly polluted. Most landfills attempt to contain leachate at the site and prevent its discharge to surface or groundwaters. To retain leachate within a disposal area, subsurface barriers of materials such as concrete, asphalt, butyl rubber, vinyl, and clay are used. It is difficult to assure that these materials can seal a landfill indefinitely. When a subsurface barrier fails, the leachate enters the groundwater in a concentrated, narrow band which may bypass monitoring wells. Once a subsurface barrier has failed, repairs are time-consuming and costly, since the waste above the repair site may have to be removed. The central problem in landfill disposal is leachate control. Recent emphasis has been on developing subsurface barriers to contain the wastes and any leachate. Future emphasis should also be on techniques for removing water from hazardous wastes before they are placed in landfills, and on methods for preventing contact of the wastes with water during and after disposal operations. When leachate is eliminated, the problems of monitoring, and subsurface barrier failure and repair can be addressed, and a waste can be effectively isolated.A surface seal landfill design is recommended for maintaining the dry state of solid hazardous wastes and for controlling leachate. Any impervious liner is utilized over the top of the landfill to prevent surface water from seeping into the waste. The surface barrier is also the site where monitoring and maintenance activities are focused. Barrier failure can be detected by visual inspections and any repairs can be made without disturbing the waste. The surface seal landfill does not employ a subsurface barrier. The surface seal landfill successfully addresses each of the four environmental problems listed above, provided that this landfill design is utilized for dry wastes only and is located at a site which provides protection from groundwater and temporary perched water tables.

  10. Radioactive waste disposal package

    DOEpatents

    Lampe, Robert F.

    1986-11-04

    A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

  11. Radioactive waste disposal package

    DOEpatents

    Lampe, Robert F.

    1986-01-01

    A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

  12. Yucca Mountain Project Subsurface Facilities Design

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

    A. Linden; R.S. Saunders; R.J. Boutin

    2002-11-19

    Four units of the Topopah Springs formation (volcanic tuff) are considered for the proposed repository: the upper lithophysal, the middle non-lithophysal, the lower lithophysal, and the lower non-lithophysal. Yucca Mountain was recently designated the site for a proposed repository to dispose of spent nuclear fuel and high-level radioactive waste. Work is proceeding to advance the design of subsurface facilities to accommodate emplacing waste packages in the proposed repository. This paper summarized recent progress in the design of subsurface layout of the proposed repository. The original Site Recommendation (SR) concept for the subsurface design located the repository largely within the lowermore » lithophysal zone (approximately 73%) of the Topopah The Site Recommendation characterized area suitable for emplacement consisted of the primary upper block, the lower block and the southern upper block extension. The primary upper block accommodated the mandated 70,000 metric tons of heavy metal (MTHM) at a 1.45 kW/m hear heat load. Based on further study of the Site Recommendation concept, the proposed repository siting area footprint was modified to make maximum use of available site characterization data, and thus, reduce uncertainties associated with performance assessment. As a result of this study, a modified repository footprint has been proposed and is presently being review for acceptance by the DOE. A panel design concept was developed to reduce overall costs and reduce the overall emplacement schedule. This concept provides flexibility to adjust the proposed repository subsurface layout with time, as it makes it unnecessary to ''commit'' to development of a large single panel at the earliest stages of construction. A description of the underground layout configuration and influencing factors that affect the layout configuration are discussed in the report.« less

  13. Study of extraterrestrial disposal of radioactive wastes. Part 1: Space transportation and destination considerations for extraterrestrial disposal of radioactive wastes. [feasibility of using space shuttle

    NASA Technical Reports Server (NTRS)

    Thompson, R. L.; Ramler, J. R.; Stevenson, S. M.

    1974-01-01

    A feasibility study of extraterrestrial disposal of radioactive waste is reported. This report covers the initial work done on only one part of the NASA study, that evaluates and compares possible space destinations and space transportation systems. The currently planned space shuttle was found to be more cost effective than current expendable launch vehicles by about a factor of 2. The space shuttle requires a third stage to perform the waste disposal missions. Depending on the particular mission, this third stage could be either a reusable space tug or an expendable stage such as a Centaur.

  14. Safe disposal of radionuclides in low-level radioactive-waste repository sites; Low-level radioactive-waste disposal workshop, U.S. Geological Survey, July 11-16, 1987, Big Bear Lake, Calif., Proceedings

    USGS Publications Warehouse

    Bedinger, Marion S.; Stevens, Peter R.

    1990-01-01

    In the United States, low-level radioactive waste is disposed by shallow-land burial. Low-level radioactive waste generated by non-Federal facilities has been buried at six commercially operated sites; low-level radioactive waste generated by Federal facilities has been buried at eight major and several minor Federally operated sites (fig. 1). Generally, low-level radioactive waste is somewhat imprecisely defined as waste that does not fit the definition of high-level radioactive waste and does not exceed 100 nCi/g in the concentration of transuranic elements. Most low-level radioactive waste generated by non-Federal facilities is generated at nuclear powerplants; the remainder is generated primarily at research laboratories, hospitals, industrial facilities, and universities. On the basis of half lives and concentrations of radionuclides in low-level radioactive waste, the hazard associated with burial of such waste generally lasts for about 500 years. Studies made at several of the commercially and Federally operated low-level radioactive-waste repository sites indicate that some of these sites have not provided containment of waste nor the expected protection of the environment.

  15. 78 FR 65390 - Exemption From Licensing for Disposal of Low-Activity Radioactive Waste at the US Ecology Idaho...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-31

    ... Disposal of Low-Activity Radioactive Waste at the US Ecology Idaho Resource Conservation and Recovery Act..., Pennsylvania, at the US Ecology Idaho (USEI) Resource Conservation and Recovery Act (RCRA) Subtitle C disposal... from the US Ecology, Inc. (US Ecology), dated July 7, 2013 (ADAMS Accession No. ML13198A017), for...

  16. Low-Level Radioactive Waste Management in the United States: What Have We Wrought? The Richard S. Hodes, M.D. Honor Lecture Award - 12222

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

    Jacobi, Lawrence R.

    2012-07-01

    In 1979, radioactive waste disposal was an important national issue. State governors were closing the gates on the existing low-level radioactive waste disposal sites and the ultimate disposition of spent fuel was undecided. A few years later, the United States Congress thought they had solved both problems by passing the Low-Level Radioactive Waste Policy Act of 1981, which established a network of regional compacts for low-level radioactive waste disposal, and by passing the Nuclear Waste Policy Act of 1982 to set out how a final resting place for high-level waste would be determined. Upon passage of the acts, State, Regionalmore » and Federal officials went to work. Here we are some 30 years later with little to show for our combined effort. The envisioned national repository for high-level radioactive waste has not materialized. Efforts to develop the Yucca Mountain high-level radioactive waste disposal facility were abandoned after spending $13 billion on the failed project. Recently, the Blue Ribbon Commission on America's Nuclear Future issued its draft report that correctly concludes the existing policy toward high-level nuclear waste is 'all but completely broken down'. A couple of new low-level waste disposal facilities have opened since 1981, but neither were the result of efforts under the act. What the Act has done is interject a system of interstate compacts with a byzantine interstate import and export system to complicate the handling of low-level radioactive waste, with attendant costs. As this paper is being written in the fourth-quarter of 2011, after 30 years of political and bureaucratic turmoil, a new comprehensive low-level waste disposal facility at Andrews Texas is approaching its initial operating date. The Yucca Mountain project might be completed or it might not. The US Nuclear Regulatory Commission is commencing a review of their 1981 volume reduction policy statement. The Department of Energy after 26 years has yet to figure out how to implement its obligations under the 1985 amendments to the Low-Level Radioactive Waste Policy Act. But, the last three decades have not been a total loss. A great deal has been learned about radioactive waste disposal since 1979 and the efforts of the public and private sector have shaped and focused the work to be done in the future. So, this lecturer asks the question: 'What have we wrought?' to which he provides his perspective and his recommendations for radioactive waste management policy for the next 30 years. (author)« less

  17. Sandia National Laboratories performance assessment methodology for long-term environmental programs : the history of nuclear waste management.

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

    Marietta, Melvin Gary; Anderson, D. Richard; Bonano, Evaristo J.

    2011-11-01

    Sandia National Laboratories (SNL) is the world leader in the development of the detailed science underpinning the application of a probabilistic risk assessment methodology, referred to in this report as performance assessment (PA), for (1) understanding and forecasting the long-term behavior of a radioactive waste disposal system, (2) estimating the ability of the disposal system and its various components to isolate the waste, (3) developing regulations, (4) implementing programs to estimate the safety that the system can afford to individuals and to the environment, and (5) demonstrating compliance with the attendant regulatory requirements. This report documents the evolution of themore » SNL PA methodology from inception in the mid-1970s, summarizing major SNL PA applications including: the Subseabed Disposal Project PAs for high-level radioactive waste; the Waste Isolation Pilot Plant PAs for disposal of defense transuranic waste; the Yucca Mountain Project total system PAs for deep geologic disposal of spent nuclear fuel and high-level radioactive waste; PAs for the Greater Confinement Borehole Disposal boreholes at the Nevada National Security Site; and PA evaluations for disposal of high-level wastes and Department of Energy spent nuclear fuels stored at Idaho National Laboratory. In addition, the report summarizes smaller PA programs for long-term cover systems implemented for the Monticello, Utah, mill-tailings repository; a PA for the SNL Mixed Waste Landfill in support of environmental restoration; PA support for radioactive waste management efforts in Egypt, Iraq, and Taiwan; and, most recently, PAs for analysis of alternative high-level radioactive waste disposal strategies including repositories deep borehole disposal and geologic repositories in shale and granite. Finally, this report summarizes the extension of the PA methodology for radioactive waste disposal toward development of an enhanced PA system for carbon sequestration and storage systems. These efforts have produced a generic PA methodology for the evaluation of waste management systems that has gained wide acceptance within the international community. This report documents how this methodology has been used as an effective management tool to evaluate different disposal designs and sites; inform development of regulatory requirements; identify, prioritize, and guide research aimed at reducing uncertainties for objective estimations of risk; and support safety assessments.« less

  18. Support of the Iraq nuclear facility dismantlement and disposal program

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

    Coates, Roger; Cochran, John; Danneels, Jeff

    2007-07-01

    Available in abstract form only. Full text of publication follows: Iraq's former nuclear facilities contain large quantities of radioactive materials and radioactive waste. The Iraq Nuclear Facility Dismantlement and Disposal Program (the Iraq NDs Program) is a new program to decontaminate and permanently dispose of radioactive wastes in Iraq. The NDs Program is led by the Government of Iraq, under International Atomic Energy Agency (IAEA) auspices, with guidance and assistance from a number of countries. The U.S. participants include Texas Tech University and Sandia National Laboratories. A number of activities are ongoing under the broad umbrella of the Iraq NDsmore » Program: drafting a new nuclear law that will provide the legal basis for the cleanup and disposal activities; assembly and analysis of existing data; characterization of soil contamination; bringing Iraqi scientists to the world's largest symposium on radioactive waste management; touring U.S. government and private sector operating radwaste disposal facilities in the U.S., and hosting a planning workshop on the characterization and cleanup of the Al-Tuwaitha Nuclear Facility. (authors)« less

  19. Sediment properties and water movement through shallow unsaturated alluvium at an arid site for disposal of low-level radioactive waste near Beatty, Nye County, Nevada

    USGS Publications Warehouse

    Fischer, Jeffrey M.

    1992-01-01

    A commercial disposal facility for low-level radioactive waste has been in operation near Beatty, Nevada, since 1962. The facility is in the arid Amargosa Desert where wastes are buried in trenches excavated into unsaturated alluvial sediments. Thick unsaturated zones in arid environments offer many potential advantages for disposal of radioactive wastes, but little is known about the natural movement of water near such facilities. Thus, a study was begun in 1982 to better define the direction and rates of water movement through the unsaturated zone in undisturbed sediments near the disposal facility. This report discusses the analyses of data collected between 1983 and 1988.

  20. SELF SINTERING OF RADIOACTIVE WASTES

    DOEpatents

    McVay, T.N.; Johnson, J.R.; Struxness, E.G.; Morgan, K.Z.

    1959-12-29

    A method is described for disposal of radioactive liquid waste materials. The wastes are mixed with clays and fluxes to form a ceramic slip and disposed in a thermally insulated container in a layer. The temperature of the layer rises due to conversion of the energy of radioactivity to heat boillng off the liquid to fomn a dry mass. The dry mass is then covered with thermal insulation, and the mass is self-sintered into a leach-resistant ceramic cake by further conversion of the energy of radioactivity to heat.

  1. Feasibility of space disposal of radioactive nuclear waste. 2: Technical summary

    NASA Technical Reports Server (NTRS)

    1974-01-01

    The feasibility of transporting radioactive waste produced in the process of generating electricity in nuclear powerplants into space for ultimate disposal was investigated at the request of the AEC as a NASA in-house effort. The investigation is part of a broad AEC study of methods for long-term storage or disposal of radioactive waste. The results of the study indicate that transporting specific radioactive wastes, particularly the actinides with very long half-lives, into space using the space shuttle/tug as the launch system, appears feasible from the engineering and safety viewpoints. The space transportation costs for ejecting the actinides out of the solar system would represent less than a 5-percent increase in the average consumer's electric bill.

  2. Remediation of a Former USAF Radioactive Material Disposal Site

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

    Hoffman, D. E.; Cushman, M; Tupyi, B.

    2003-02-25

    This paper describes the remediation of a low-level radiological waste burial site located at the former James Connally Air Force Base in Waco, Texas. Burial activities at the site occurred during the 1950's when the property was under the ownership of the United States Air Force. Included is a discussion of methods and strategies that were used to successfully exhume and characterize the wastes for proper disposal at offsite disposal facilities. Worker and environmental protection measures are also described. Information gained from this project may be used at other similar project sites. A total of nine burial tubes had beenmore » identified for excavation, characterization, and removal from the site. The disposal tubes were constructed of 4-ft lengths of concrete pipe buried upright with the upper ends flush with ground surface. Initial ground level observations of the burial tubes indicated that some weathering had occurred; however, the condition of the subsurface portions of the tubes was unknown. Soil excavation occurred in 1-foot lifts in order that the tubes could be inspected and to allow for characterization of the soils at each stage of the excavation. Due to the weight of the concrete pipe and the condition of the piping joints it was determined that special measures would be required to maintain the tubes intact during their removal. Special tube anchoring and handling methods were required to relocate the tubes from their initial positions to a staging area where they could be further characterized. Characterization of the disposal tubes was accomplished using a combination of gamma spectroscopy and activity mapping methods. Important aspects of the project included the use of specialized excavation and disposal tube reinforcement measures to maintain the disposal tubes intact during excavation, removal and subsequent characterization. The non-intrusive gamma spectroscopy and data logging methods allowed for effective characterization of the wastes while minimizing disposal costs. In addition, worker exposures were maintained ALARA as a result of the removal and characterization methods employed.« less

  3. NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA

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

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

    This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal.

  4. Journey to the Nevada Test Site Radioactive Waste Management Complex

    ScienceCinema

    None

    2018-01-16

    Journey to the Nevada Test Site Radioactive Waste Management Complex begins with a global to regional perspective regarding the location of low-level and mixed low-level waste disposal at the Nevada Test Site. For decades, the Nevada National Security Site (NNSS) has served as a vital disposal resource in the nation-wide cleanup of former nuclear research and testing facilities. State-of-the-art waste management sites at the NNSS offer a safe, permanent disposal option for U.S. Department of Energy/U.S. Department of Defense facilities generating cleanup-related radioactive waste.

  5. Water Migration and Swelling in Bentonite Quantified using Neutron Radiography

    NASA Astrophysics Data System (ADS)

    Vial, A.; DiStefano, V. H.; Perfect, E.; Hale, R. E.; Anovitz, L. M.; McFarlane, J.

    2016-12-01

    Permanent disposal of radioactive waste remains a critical challenge for the nation's energy future. All disposal system concepts include interfaces between engineered systems and natural materials requiring extensive characterization. Bentonite is often used to buffer subsurface disposal systems from geologic media containing ground water. Bentonite characterization experiments were carried out using the CG-1D neutron imaging beam line at Oak Ridge National Laboratory. Dry bentonite was packed into vertically-oriented aluminum cylinders. Water was ponded on the top surface of each packed cylinder. Images were acquired at 2 min intervals using dynamic neutron radiography. The detector consisted of stacked neutron sensitive microchannel plates above a quad Timepix readout with a 28 x 28 mm2 field of view. The spatial resolution of the detector was 55 μm. Raw neutron radiographs were imported into ImageJ and normalized with respect to the initial completely dry state. The wetting process was 1-dimensional, and vertical intensity profiles were computed by averaging pixel rows. The vertical distance between the clay-water interface and the wetting front could then be determined as a function of time. Depth of water infiltration increased linearly with the square root of time, yielding a sorptivity value of 0.75 (± 0.070) mm/min0.5. Swelling occurred in the form of upward movement of clay particles into the ponded water over time. The resulting low density assemblage was discernable by normalizing the raw profiles with respect to the intensity profile immediately after ponding. The packed clay-water interface was clearly visible in the normalized profiles, and swelling was quantified as the height of the low density assemblage above the original interface. Swelling occurred as a linear function of time, at a rate of 0.054 (± 0.020) mm/min. Further experiments of this type are planned under variable temperature and pressure regimes applicable to subsurface repositories.

  6. License restrictions at Barnwell

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

    Autry, V.R.

    1991-12-31

    The State of South Carolina was delegated the authority by the US Nuclear Regulatory Commission to regulate the receipt, possession, use and disposal of radioactive material as an Agreement State. Since 1970, the state has been the principal regulatory authority for the Barnwell Low-Level Waste Disposal Facility operated by Chem-Nuclear Systems, Inc. The radioactive material license issued authorizing the receipt and disposal of low-level waste contains numerous restrictions to ensure environmental protection and compliance with shallow land disposal performance criteria. Low-level waste has evolved from minimally contaminated items to complex waste streams containing high concentrations of radionuclides and processing chemicalsmore » which necessitated these restrictions. Additionally, some waste with their specific radionuclides and concentration levels, many classified as low-level radioactive waste, are not appropriate for shallow land disposal unless additional precautions are taken. This paper will represent a number of these restrictions, the rationale for them, and how they are being dealt with at the Barnwell disposal facility.« less

  7. 10 CFR 39.45 - Subsurface tracer studies.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Subsurface tracer studies. 39.45 Section 39.45 Energy NUCLEAR REGULATORY COMMISSION LICENSES AND RADIATION SAFETY REQUIREMENTS FOR WELL LOGGING Equipment § 39.45 Subsurface tracer studies. (a) The licensee shall require all personnel handling radioactive...

  8. 10 CFR 39.45 - Subsurface tracer studies.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Subsurface tracer studies. 39.45 Section 39.45 Energy NUCLEAR REGULATORY COMMISSION LICENSES AND RADIATION SAFETY REQUIREMENTS FOR WELL LOGGING Equipment § 39.45 Subsurface tracer studies. (a) The licensee shall require all personnel handling radioactive...

  9. 10 CFR 61.1 - Purpose and scope.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.1 Purpose and scope. (a) The regulations in this part establish, for land disposal of radioactive waste, the procedures, criteria, and terms and conditions upon which the Commission issues...

  10. 10 CFR 61.1 - Purpose and scope.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.1 Purpose and scope. (a) The regulations in this part establish, for land disposal of radioactive waste, the procedures, criteria, and terms and conditions upon which the Commission issues...

  11. 10 CFR 61.1 - Purpose and scope.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.1 Purpose and scope. (a) The regulations in this part establish, for land disposal of radioactive waste, the procedures, criteria, and terms and conditions upon which the Commission issues...

  12. 10 CFR 61.1 - Purpose and scope.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.1 Purpose and scope. (a) The regulations in this part establish, for land disposal of radioactive waste, the procedures, criteria, and terms and conditions upon which the Commission issues...

  13. 10 CFR 61.1 - Purpose and scope.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE General Provisions § 61.1 Purpose and scope. (a) The regulations in this part establish, for land disposal of radioactive waste, the procedures, criteria, and terms and conditions upon which the Commission issues...

  14. Report of ICRP Task Group 80: 'radiological protection in geological disposal of long-lived solid radioactive waste'.

    PubMed

    Weiss, W

    2012-01-01

    The report of International Commission on Radiological Protection (ICRP) Task Group 80 entitled 'Radiological protection in geological disposal of long-lived solid radioactive waste' updates and consolidates previous ICRP recommendations related to solid waste disposal (ICRP Publications 46, 77, and 81). The recommendations given in this report apply specifically to geological disposal of long-lived solid radioactive waste. The report explains how the 2007 system of radiological protection, described in ICRP Publication 103, can be applied in the context of the geological disposal of long-lived solid radioactive waste. The report is written as a self-standing document. It describes the different stages in the lifetime of a geological disposal facility, and addresses the application of relevant radiological protection principles for each stage depending on the various exposure situations that can be encountered. In particular, the crucial factor that influences application of the protection system over the different phases in the lifetime of a disposal facility is the level of oversight that is present. The level of oversight affects the capability to reduce or avoid exposures. Three main time frames have to be considered for the purpose of radiological protection: time of direct oversight when the disposal facility is being implemented and active oversight is taking place; time of indirect oversight when the disposal facility is sealed and indirect oversight is being exercised to provide additional assurance on behalf of the population; and time of no oversight when oversight is no longer exercised because memory is lost. Copyright © 2012. Published by Elsevier Ltd.

  15. Deep Borehole Disposal Concept: Development of Universal Canister Concept of Operations

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

    Rigali, Mark J.; Price, Laura L.

    This report documents key elements of the conceptual design for deep borehole disposal of radioactive waste to support the development of a universal canister concept of operations. A universal canister is a canister that is designed to be able to store, transport, and dispose of radioactive waste without the canister having to be reopened to treat or repackage the waste. This report focuses on the conceptual design for disposal of radioactive waste contained in a universal canister in a deep borehole. The general deep borehole disposal concept consists of drilling a borehole into crystalline basement rock to a depth ofmore » about 5 km, emplacing WPs in the lower 2 km of the borehole, and sealing and plugging the upper 3 km. Research and development programs for deep borehole disposal have been ongoing for several years in the United States and the United Kingdom; these studies have shown that deep borehole disposal of radioactive waste could be safe, cost effective, and technically feasible. The design concepts described in this report are workable solutions based on expert judgment, and are intended to guide follow-on design activities. Both preclosure and postclosure safety were considered in the development of the reference design concept. The requirements and assumptions that form the basis for the deep borehole disposal concept include WP performance requirements, radiological protection requirements, surface handling and transport requirements, and emplacement requirements. The key features of the reference disposal concept include borehole drilling and construction concepts, WP designs, and waste handling and emplacement concepts. These features are supported by engineering analyses.« less

  16. 10 CFR 39.45 - Subsurface tracer studies.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 1 2013-01-01 2013-01-01 false Subsurface tracer studies. 39.45 Section 39.45 Energy....45 Subsurface tracer studies. (a) The licensee shall require all personnel handling radioactive tracer material to use protective gloves and, if required by the license, other protective clothing and...

  17. 10 CFR 39.45 - Subsurface tracer studies.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 1 2012-01-01 2012-01-01 false Subsurface tracer studies. 39.45 Section 39.45 Energy....45 Subsurface tracer studies. (a) The licensee shall require all personnel handling radioactive tracer material to use protective gloves and, if required by the license, other protective clothing and...

  18. 10 CFR 39.45 - Subsurface tracer studies.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 1 2014-01-01 2014-01-01 false Subsurface tracer studies. 39.45 Section 39.45 Energy....45 Subsurface tracer studies. (a) The licensee shall require all personnel handling radioactive tracer material to use protective gloves and, if required by the license, other protective clothing and...

  19. DOE`s radioactively - contaminated metal recycling: The policy and its implementation

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

    Warren, S.; Rizkalla, E.

    1997-02-01

    In 1994, the Department of Energy`s Office of Environmental Restoration initiated development of a recycling policy to minimize the amount of radioactively-contaminated metal being disposed of as waste. During the following two years, stakeholders (including DOE and contractor personnel, regulators, members of the public, and representatives of labor and industry) were invited to identify key issues of concern, and to provide input on the final policy. As a result of this process, a demonstration policy for recycling radioactively-contaminated carbon steel resulting from decommissioning activities within the Environmental Management program was signed on September 20, 1996. It specifically recognizes that themore » Office of Environmental Management has a tremendous opportunity to minimize the disposal of metals as waste by the use of disposal containers fabricated from contaminated steel. The policy further recognizes the program`s demand for disposal containers, and it`s role as the major generator of radioactively-contaminated steel.« less

  20. Polonium-210 in the environment around a radioactive waste disposal area and phosphate ore processing plant.

    PubMed

    Arthur, W J; Markham, O D

    1984-04-01

    Polonium-210 concentrations were determined for soil, vegetation and small mammal tissues collected at a solid radioactive waste disposal area, near a phosphate ore processing plant and at two rural areas in southeastern Idaho. Polonium concentrations in media sampled near the radioactive waste disposal facility were equal to or less than values from rural area samples, indicating that disposal of solid radioactive waste at the Idaho National Engineering Laboratory Site has not resulted in increased environmental levels of polonium. Concentrations of 210Po in soils, deer mice hide and carcass samples collected near the phosphate processing plant were statistically (P less than or equal to 0.05) greater than the other sampling locations; however, the mean 210Po concentration in soils and small mammal tissues from sampling areas near the phosphate plant were only four and three times greater, respectively, than control values. No statistical (P greater than 0.05) difference was observed for 210Po concentrations in vegetation among any of the sampling locations.

  1. Geohydrology of the near-surface unsaturated zone adjacent to the disposal site for low-level radioactive waste near Beatty, Nevada: A section in Safe disposal of radionuclides in low-level radioactive-waste repository sites; Low-level radioactive-waste disposal workshop, U.S. Geological Survey, July 11-16, 1987, Big Bear Lake, Calif., Proceedings (Circular 1036)

    USGS Publications Warehouse

    Fisher, Jeffrey M.; Bedinger, Marion S.; Stevens, Peter R.

    1990-01-01

    Shallow-land burial in arid areas is considered the best method for isolating low-level radioactive waste from the environment (Nichols and Goode, this report; Mercer and others, 1983). A major threat to waste isolation in shallow trenches is ground-water percolation. Repository sites in arid areas are believed to minimize the risk of ground-water contamination because such sites receive minimal precipitation and are underlain by thick unsaturated zones. Unfortunately, few data are available on rates of water percolation in an arid environment.

  2. Safety monitoring of the FBG sensor in respect of radioactivity and deformation measurement of a silo structure for radioactive waste disposal

    NASA Astrophysics Data System (ADS)

    Kim, Ki-Soo; Cho, Seong-Kyu

    2015-07-01

    The FBG sensor has globally been commercialized in various fields that is actively applied in Korea as well. Especially it is widely used as a structural monitoring sensor in civil engineering and construction structures due to its advantages including electrical stability, chemical stability and multiplexing. This report aims to introduce safety inspection of the FBG sensor in respect of radioactivity which has been applied to a silo structure for radioactive waste disposal as an example.

  3. Radioactive Wastes.

    PubMed

    Choudri, B S; Charabi, Yassine; Baawain, Mahad; Ahmed, Mushtaque

    2017-10-01

    Papers reviewed herein present a general overview of radioactive waste related activities around the world in 2016. The current reveiw include studies related to safety assessments, decommission and decontamination of nuclear facilities, fusion facilities, transportation. Further, the review highlights on management solutions for the final disposal of low and high level radioactive wastes (LLW and HLW), interim storage and final disposal options for spent fuel (SF), and tritiated wastes, with a focus on environmental impacts due to the mobility of radionuclides in ecosystem, water and soil alongwith other progress made in the management of radioactive wastes.

  4. Effect of biogas generation on radon emissions from landfills receiving radium-bearing waste from shale gas development.

    PubMed

    Walter, Gary R; Benke, Roland R; Pickett, David A

    2012-09-01

    Dramatic increases in the development of oil and natural gas from shale formations will result in large quantities of drill cuttings, flowback water, and produced water. These organic-rich shale gas formations often contain elevated concentrations of naturally occurring radioactive materials (NORM), such as uranium, thorium, and radium. Production of oil and gas from these formations will also lead to the development of technologically enhanced NORM (TENORM) in production equipment. Disposal of these potentially radium-bearing materials in municipal solid waste (MSW) landfills could release radon to the atmosphere. Risk analyses of disposal of radium-bearing TENORM in MSW landfills sponsored by the Department of Energy did not consider the effect of landfill gas (LFG) generation or LFG control systems on radon emissions. Simulation of radon emissions from landfills with LFG generation indicates that LFG generation can significantly increase radon emissions relative to emissions without LFG generation, where the radon emissions are largely controlled by vapor-phase diffusion. Although the operation of LFG control systems at landfills with radon source materials can result in point-source atmospheric radon plumes, the LFG control systems tend to reduce overall radon emissions by reducing advective gas flow through the landfill surface, and increasing the radon residence time in the subsurface, thus allowing more time for radon to decay. In some of the disposal scenarios considered, the radon flux from the landfill and off-site atmospheric activities exceed levels that would be allowed for radon emissions from uranium mill tailings. Increased development of hydrocarbons from organic-rich shale formations has raised public concern that wastes from these activities containing naturally occurring radioactive materials, particularly radium, may be disposed in municipal solid waste landfills and endanger public health by releasing radon to the atmosphere. This paper analyses the processes by which radon may be emitted from a landfill to the atmosphere. The analyses indicate that landfill gas generation can significantly increase radon emissions, but that the actual level of radon emissions depend on the place of the waste, construction of the landfill cover, and nature of the landfill gas control system.

  5. 10 CFR 61.50 - Disposal site suitability requirements for land disposal.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Disposal site suitability requirements for land disposal. 61.50 Section 61.50 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.50 Disposal site...

  6. 10 CFR 61.51 - Disposal site design for land disposal.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Disposal site design for land disposal. 61.51 Section 61.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.51 Disposal site design for land...

  7. 10 CFR 61.50 - Disposal site suitability requirements for land disposal.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Disposal site suitability requirements for land disposal. 61.50 Section 61.50 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.50 Disposal site...

  8. 10 CFR 61.51 - Disposal site design for land disposal.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Disposal site design for land disposal. 61.51 Section 61.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.51 Disposal site design for land...

  9. 10 CFR 61.51 - Disposal site design for land disposal.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Disposal site design for land disposal. 61.51 Section 61.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.51 Disposal site design for land...

  10. 10 CFR 61.51 - Disposal site design for land disposal.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Disposal site design for land disposal. 61.51 Section 61.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.51 Disposal site design for land...

  11. 10 CFR 61.50 - Disposal site suitability requirements for land disposal.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Disposal site suitability requirements for land disposal. 61.50 Section 61.50 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.50 Disposal site...

  12. 10 CFR 61.50 - Disposal site suitability requirements for land disposal.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Disposal site suitability requirements for land disposal. 61.50 Section 61.50 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.50 Disposal site...

  13. 10 CFR 61.50 - Disposal site suitability requirements for land disposal.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Disposal site suitability requirements for land disposal. 61.50 Section 61.50 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.50 Disposal site...

  14. 10 CFR 61.51 - Disposal site design for land disposal.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Disposal site design for land disposal. 61.51 Section 61.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.51 Disposal site design for land...

  15. 10 CFR 961.2 - Applicability.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... ENERGY STANDARD CONTRACT FOR DISPOSAL OF SPENT NUCLEAR FUEL AND/OR HIGH-LEVEL RADIOACTIVE WASTE General... owns or generates spent nuclear fuel or high-level radioactive waste, of domestic origin, generated in... part will commit DOE to accept title to, transport, and dispose of such spent fuel and waste. In...

  16. 10 CFR 61.28 - Contents of application for closure.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.28 Contents of application for closure. (a) Prior to final closure of the disposal... site data pertinent to the long-term containment of emplaced radioactive wastes obtained during the...

  17. 10 CFR 61.28 - Contents of application for closure.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.28 Contents of application for closure. (a) Prior to final closure of the disposal... site data pertinent to the long-term containment of emplaced radioactive wastes obtained during the...

  18. 10 CFR 61.28 - Contents of application for closure.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.28 Contents of application for closure. (a) Prior to final closure of the disposal... site data pertinent to the long-term containment of emplaced radioactive wastes obtained during the...

  19. 10 CFR 61.28 - Contents of application for closure.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.28 Contents of application for closure. (a) Prior to final closure of the disposal... site data pertinent to the long-term containment of emplaced radioactive wastes obtained during the...

  20. 10 CFR 61.28 - Contents of application for closure.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.28 Contents of application for closure. (a) Prior to final closure of the disposal... site data pertinent to the long-term containment of emplaced radioactive wastes obtained during the...

  1. Volatile organic compounds in the unsaturated zone from radioactive wastes

    USGS Publications Warehouse

    Baker, Ronald J.; Andraski, Brian J.; Stonestrom, David A.; Luo, Wentai

    2012-01-01

    Volatile organic compounds (VOCs) are often comingled with low-level radioactive wastes (LLRW), but little is known about subsurface VOC emanations from LLRW landfills. The current study systematically quantified VOCs associated with LLRW over an 11-yr period at the USGS Amargosa Desert Research Site (ADRS) in southwestern Nevada. Unsaturated-zone gas samples of VOCs were collected by adsorption on resin cartridges and analyzed by thermal desorption and GC/MS. Sixty of 87 VOC method analytes were detected in the 110-m-thick unsaturated zone surrounding a LLRW disposal facility. Chlorofluorocarbons (CFCs) were detected in 100% of samples collected. Chlorofluorocarbons are powerful greenhouse gases, deplete stratospheric ozone, and are likely released from LLRW facilities worldwide. Soil-gas samples collected from a depth of 24 m and a horizontal distance 100 m south of the nearest waste-disposal trench contained >60,000 ppbv total VOCs, including >37,000 ppbv CFCs. Extensive sampling in the shallow unsaturated zone (0–2 m deep) identified areas where total VOC concentrations exceeded 5000 ppbv at the 1.5-m depth. Volatile organic compound concentrations exceeded background levels up to 300 m from the facility. Maximum vertical diffusive fluxes of total VOCs were estimated to be 1 g m-2 yr-1. Volatile organic compound distributions were similar but not identical to those previously determined for tritium and elemental mercury. To our knowledge, this study is the first to characterize the unsaturated zone distribution of VOCs emanating from a LLRW landfill. Our results may help explain anomalous transport of radionuclides at the ADRS and elsewhere.

  2. Use of petrophysical data for siting of deep geological repository of radioactive waste

    NASA Astrophysics Data System (ADS)

    Petrenko, Liliana; Shestopalov, Vyacheslav

    2017-11-01

    The paper is devoted to analyzing the petrophysical properties and petrographical characteristics of Volyn region with the view to choosing the least permeable and so the most suitable geological formation for the radioactive waste disposal. On a basis of the petrophysical estimations of the granitoids properties the argumentation of permeability has been developed for the petrotypes of Volyn region. Also method of classification of the petrotypes with their relative rate of suitability for radioactive waste disposal was developed. As a result of studying the perspectives were shown of the zhytomyr and korosten types of the granitoids as host rock for the radioactive waste disposal. According to the results of investigations performed by Swedish researchers a comparative analysis of rocks based on the age of formation, composition, structural features and some petrophysical properties of granitoids as host rocks for repository of radioactive waste was performed. Detail comparison the data of the granitoids of the Forsmark site in Sweden and the data of the granitoids of the Volyn megablock can be one of the next steps in researching the host rocks for the development of the RW disposal system in Ukraine.

  3. Lessons Learned from Radioactive Waste Storage and Disposal Facilities

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

    Esh, David W.; Bradford, Anna H.

    2008-01-15

    The safety of radioactive waste disposal facilities and the decommissioning of complex sites may be predicated on the performance of engineered and natural barriers. For assessing the safety of a waste disposal facility or a decommissioned site, a performance assessment or similar analysis is often completed. The analysis is typically based on a site conceptual model that is developed from site characterization information, observations, and, in many cases, expert judgment. Because waste disposal facilities are sited, constructed, monitored, and maintained, a fair amount of data has been generated at a variety of sites in a variety of natural systems. Thismore » paper provides select examples of lessons learned from the observations developed from the monitoring of various radioactive waste facilities (storage and disposal), and discusses the implications for modeling of future waste disposal facilities that are yet to be constructed or for the development of dose assessments for the release of decommissioning sites. Monitoring has been and continues to be performed at a variety of different facilities for the disposal of radioactive waste. These include facilities for the disposal of commercial low-level waste (LLW), reprocessing wastes, and uranium mill tailings. Many of the lessons learned and problems encountered provide a unique opportunity to improve future designs of waste disposal facilities, to improve dose modeling for decommissioning sites, and to be proactive in identifying future problems. Typically, an initial conceptual model was developed and the siting and design of the disposal facility was based on the conceptual model. After facility construction and operation, monitoring data was collected and evaluated. In many cases the monitoring data did not comport with the original site conceptual model, leading to additional investigation and changes to the site conceptual model and modifications to the design of the facility. The following cases are discussed: commercial LLW disposal facilities; uranium mill tailings disposal facilities; and reprocessing waste storage and disposal facilities. The observations developed from the monitoring and maintenance of waste disposal and storage facilities provide valuable lessons learned for the design and modeling of future waste disposal facilities and the decommissioning of complex sites.« less

  4. 77 FR 34229 - Idaho: Final Authorization of State Hazardous Waste Management Program; Revision

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-06-11

    ... capability for the disposal of remote-handled low-level radioactive waste ((LLW) generated at the Idaho... (FONSI), for the Remote-Handled Low-Level Radioactive Waste Onsite Disposal (RHLLWOD) on an Environmental... regulating phosphate (mineral processing) plants within the state. In response to this commenter's concerns...

  5. Deep Borehole Field Test Requirements and Controlled Assumptions.

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

    Hardin, Ernest

    2015-07-01

    This document presents design requirements and controlled assumptions intended for use in the engineering development and testing of: 1) prototype packages for radioactive waste disposal in deep boreholes; 2) a waste package surface handling system; and 3) a subsurface system for emplacing and retrieving packages in deep boreholes. Engineering development and testing is being performed as part of the Deep Borehole Field Test (DBFT; SNL 2014a). This document presents parallel sets of requirements for a waste disposal system and for the DBFT, showing the close relationship. In addition to design, it will also inform planning for drilling, construction, and scientificmore » characterization activities for the DBFT. The information presented here follows typical preparations for engineering design. It includes functional and operating requirements for handling and emplacement/retrieval equipment, waste package design and emplacement requirements, borehole construction requirements, sealing requirements, and performance criteria. Assumptions are included where they could impact engineering design. Design solutions are avoided in the requirements discussion. Deep Borehole Field Test Requirements and Controlled Assumptions July 21, 2015 iv ACKNOWLEDGEMENTS This set of requirements and assumptions has benefited greatly from reviews by Gordon Appel, Geoff Freeze, Kris Kuhlman, Bob MacKinnon, Steve Pye, David Sassani, Dave Sevougian, and Jiann Su.« less

  6. A comprehensive inventory of radiological and nonradiological contaminants in waste buried or projected to be buried in the subsurface disposal area of the INEL RWMC during the years 1984-2003, Volume 3

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

    NONE

    1995-05-01

    This is the third volume of this comprehensive report of the inventory of radiological and nonradiological contaminants in waste buried or projected to be buried in the subsurface disposal area of the Idaho National Engineering Laboratory. Appendix B contains a complete printout of contaminant inventory and other information from the CIDRA Database and is presented in volumes 2 and 3 of the report.

  7. 25 Years of DECOVALEX - Research Advances and Lessons Learned from an International Model Comparison Initiative

    NASA Astrophysics Data System (ADS)

    Birkholzer, J. T.

    2017-12-01

    This presentation provides an overview of an international research and model comparison collaboration (DECOVALEX) for advancing the understanding and modeling of coupled thermo-hydro-mechanical-chemical (THMC) processes in geological systems. Prediction of these coupled effects is an essential part of the performance and safety assessment of geologic disposal systems for radioactive waste and spent nuclear fuel, and is also relevant for a range of other sub-surface engineering activities. DECOVALEX research activities have been supported by a large number of radioactive-waste-management organizations and regulatory authorities. Research teams from more than a dozen international partner organizations have participated in the comparative modeling evaluation of complex field and laboratory experiments in the UK, Switzerland, Japan, France and Sweden. Together, these tasks (1) have addressed a wide range of relevant issues related to engineered and natural system behavior in argillaceous, crystalline and other host rocks, (2) have yielded in-depth knowledge of coupled THM and THMC processes associated with nuclear waste repositories and wider geo-engineering applications, and (3) have advanced the capability, as well as demonstrated the suitability, of numerical simulation models for quantitative analysis.

  8. 10 CFR 61.12 - Specific technical information.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE... of the land disposal facility and the disposal units. For near-surface disposal, the description must...; structural stability of backfill, wastes, and covers; contact of wastes with standing water; disposal site...

  9. 10 CFR 61.12 - Specific technical information.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE... of the land disposal facility and the disposal units. For near-surface disposal, the description must...; structural stability of backfill, wastes, and covers; contact of wastes with standing water; disposal site...

  10. 10 CFR 61.12 - Specific technical information.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE... of the land disposal facility and the disposal units. For near-surface disposal, the description must...; structural stability of backfill, wastes, and covers; contact of wastes with standing water; disposal site...

  11. 10 CFR 61.12 - Specific technical information.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE... of the land disposal facility and the disposal units. For near-surface disposal, the description must...; structural stability of backfill, wastes, and covers; contact of wastes with standing water; disposal site...

  12. 10 CFR 61.12 - Specific technical information.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE... of the land disposal facility and the disposal units. For near-surface disposal, the description must...; structural stability of backfill, wastes, and covers; contact of wastes with standing water; disposal site...

  13. On policies to regulate long-term risks from hazardous waste disposal sites under both intergenerational equity and intragenerational equity

    NASA Astrophysics Data System (ADS)

    Shu, Zhongbin

    In recent years, it has been recognized that there is a need for a general philosophic policy to guide the regulation of societal activities that involve long-term and very long-term risks. Theses societal activities not only include the disposal of high-level radioactive wastes and global warming, but also include the disposal of non-radioactive carcinogens that never decay, such as arsenic, nickel, etc. In the past, attention has been focused on nuclear wastes. However, there has been international recognition that large quantities of non-radioactive wastes are being disposed of with little consideration of their long-term risks. The objectives of this dissertation are to present the significant long-term risks posed by non-radioactive carcinogens through case studies; develop the conceptual decision framework for setting the long-term risk policy; and illustrate that certain factors, such as discount rate, can significantly influence the results of long-term risk analysis. Therefore, the proposed decision-making framework can be used to systematically study the important policy questions on long-term risk regulations, and then subsequently help the decision-maker to make informed decisions. Regulatory disparities between high-level radioactive wastes and non-radioactive wastes are summarized. Long-term risk is rarely a consideration in the regulation of disposal of non-radioactive hazardous chemicals; and when it is, the matter has been handled in a somewhat perfunctory manner. Case studies of long-term risks are conducted for five Superfund sites that are contaminated with one or more non-radioactive carcinogens. Under the same assumptions used for the disposal of high-level radioactive wastes, future subsistence farmers would be exposed to significant individual risks, in some cases with lifetime fatality risk equal to unity. The important policy questions on long-term risk regulation are identified, and the conceptual decision-making framework to regulate long-term risk is presented. The results of decision tree analysis of cleanup alternatives for the Crystal Chemical site indicate that discount rate has profound impact on the results of the analysis and significant implication with regard to intergenerational equity. It is expected that other policy factors could have similar impacts. There is a need to use the proposed decision-making framework to systemically study those factors and make rational policy decisions accordingly.

  14. 20 CFR 654.406 - Excreta and liquid waste disposal.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... subsurface septic tank-seepage system or other type of liquid waste treatment and disposal system, privies or... RESPONSIBILITIES OF THE EMPLOYMENT SERVICE SYSTEM Housing for Agricultural Workers Housing Standards § 654.406... accumulate on the ground surface. (b) Where public sewer systems are available, all facilities for disposal...

  15. 20 CFR 654.406 - Excreta and liquid waste disposal.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... subsurface septic tank-seepage system or other type of liquid waste treatment and disposal system, privies or... RESPONSIBILITIES OF THE EMPLOYMENT SERVICE SYSTEM Housing for Agricultural Workers Housing Standards § 654.406... accumulate on the ground surface. (b) Where public sewer systems are available, all facilities for disposal...

  16. 20 CFR 654.406 - Excreta and liquid waste disposal.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... subsurface septic tank-seepage system or other type of liquid waste treatment and disposal system, privies or... RESPONSIBILITIES OF THE EMPLOYMENT SERVICE SYSTEM Housing for Agricultural Workers Housing Standards § 654.406... accumulate on the ground surface. (b) Where public sewer systems are available, all facilities for disposal...

  17. 20 CFR 654.406 - Excreta and liquid waste disposal.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... subsurface septic tank-seepage system or other type of liquid waste treatment and disposal system, privies or... RESPONSIBILITIES OF THE EMPLOYMENT SERVICE SYSTEM Housing for Agricultural Workers Housing Standards § 654.406... accumulate on the ground surface. (b) Where public sewer systems are available, all facilities for disposal...

  18. 20 CFR 654.406 - Excreta and liquid waste disposal.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... subsurface septic tank-seepage system or other type of liquid waste treatment and disposal system, privies or... RESPONSIBILITIES OF THE EMPLOYMENT SERVICE SYSTEM Housing for Agricultural Workers Housing Standards § 654.406... accumulate on the ground surface. (b) Where public sewer systems are available, all facilities for disposal...

  19. Hydrogeologic factors in the selection of shallow land burial sites for the disposal of low-level radioactive waste

    USGS Publications Warehouse

    Fischer, John N.

    1986-01-01

    In the United States, low-level radioactive waste is disposed of by shallow land burial. Commercial low-level radioactive waste has been buried at six sites, and low-level radioactive waste generated by the Federal Government has been buried at nine major and several minor sites. Several existing low-level radioactive waste sites have not provided expected protection of the environment. These shortcomings are related, at least in part, to an inadequate understanding of site hydrogeology at the time the sites were selected. To better understand the natural systems and the effect of hydrogeologic factors on long-term site performance, the U.S. Geological Survey has conducted investigations at five of the six commercial low-level radioactive waste sites and at three Federal sites. These studies, combined with those of other Federal and State agencies, have identified and confirmed important hydrogeologic factors in the effective disposal of low-level radioactive waste by shallow land burial. These factors include precipitation, surface drainage, topography, site stability, geology, thickness of the host soil-rock horizon, soil and sediment permeability, soil and water chemistry, and depth to the water table.

  20. Illustrative assessment of human health issues arising from the potential release of chemotoxic substances from a generic geological disposal facility for radioactive waste.

    PubMed

    Wilson, James C; Thorne, Michael C; Towler, George; Norris, Simon

    2011-12-01

    Many countries have a programme for developing an underground geological disposal facility for radioactive waste. A case study is provided herein on the illustrative assessment of human health issues arising from the potential release of chemotoxic and radioactive substances from a generic geological disposal facility (GDF) for radioactive waste. The illustrative assessment uses a source-pathway-receptor methodology and considers a number of human exposure pathways. Estimated exposures are compared with authoritative toxicological assessment criteria. The possibility of additive and synergistic effects resulting from exposures to mixtures of chemical contaminants or a combination of radiotoxic and chemotoxic substances is considered. The case study provides an illustration of how to assess human health issues arising from chemotoxic species released from a GDF for radioactive waste and highlights potential difficulties associated with a lack of data being available with which to assess synergistic effects. It also highlights how such difficulties can be addressed.

  1. Monte Carlo simulations of radioactive waste encapsulated by bisphenol-A polycarbonate and effect of bismuth-III oxide filler material

    NASA Astrophysics Data System (ADS)

    Özdemir, Tonguç

    2017-06-01

    Radioactive waste generated from the nuclear industry and non-power applications should carefully be treated, conditioned and disposed according to the regulations set by the competent authority(ies). Bisphenol-a polycarbonate (BPA-PC), a very widely used polymer, might be considered as a potential candidate material for low level radioactive waste encapsulation. In this work, the dose rate distribution in the radioactive waste drum (containing radioactive waste and the BPA-PC polymer matrix) was determined using Monte Carlo simulations. Moreover, the change of mechanical properties of BPA-PC was estimated and their variation within the waste drum was determined for the periods of 15, 30 and 300 years after disposal to the final disposal site. The change of the dose rate within the waste drum with different contents of bismuth-III oxide were also simulated. It was concluded that addition of bismuth-III oxide filler decreases the dose delivered to the polymeric matrix due to photoelectric effect.

  2. Real-time gamma imaging of technetium transport through natural and engineered porous materials for radioactive waste disposal.

    PubMed

    Corkhill, Claire L; Bridge, Jonathan W; Chen, Xiaohui C; Hillel, Phil; Thornton, Steve F; Romero-Gonzalez, Maria E; Banwart, Steven A; Hyatt, Neil C

    2013-12-03

    We present a novel methodology for determining the transport of technetium-99m, a γ-emitting metastable isomer of (99)Tc, through quartz sand and porous media relevant to the disposal of nuclear waste in a geological disposal facility (GDF). Quartz sand is utilized as a model medium, and the applicability of the methodology to determine radionuclide transport in engineered backfill cement is explored using the UK GDF candidate backfill cement, Nirex Reference Vault Backfill (NRVB), in a model system. Two-dimensional distributions in (99m)Tc activity were collected at millimeter-resolution using decay-corrected gamma camera images. Pulse-inputs of ~20 MBq (99m)Tc were introduced into short (<10 cm) water-saturated columns at a constant flow of 0.33 mL min(-1). Changes in calibrated mass distribution of (99m)Tc at 30 s intervals, over a period of several hours, were quantified by spatial moments analysis. Transport parameters were fitted to the experimental data using a one-dimensional convection-dispersion equation, yielding transport properties for this radionuclide in a model GDF environment. These data demonstrate that (99)Tc in the pertechnetate form (Tc(VII)O4(-)) does not sorb to cement backfill during transport under model conditions, resulting in closely conservative transport behavior. This methodology represents a quantitative development of radiotracer imaging and offers the opportunity to conveniently and rapidly characterize transport of gamma-emitting isotopes in opaque media, relevant to the geological disposal of nuclear waste and potentially to a wide variety of other subsurface environments.

  3. Real-Time Gamma Imaging of Technetium Transport through Natural and Engineered Porous Materials for Radioactive Waste Disposal

    PubMed Central

    2013-01-01

    We present a novel methodology for determining the transport of technetium-99m, a γ-emitting metastable isomer of 99Tc, through quartz sand and porous media relevant to the disposal of nuclear waste in a geological disposal facility (GDF). Quartz sand is utilized as a model medium, and the applicability of the methodology to determine radionuclide transport in engineered backfill cement is explored using the UK GDF candidate backfill cement, Nirex Reference Vault Backfill (NRVB), in a model system. Two-dimensional distributions in 99mTc activity were collected at millimeter-resolution using decay-corrected gamma camera images. Pulse-inputs of ∼20 MBq 99mTc were introduced into short (<10 cm) water-saturated columns at a constant flow of 0.33 mL min–1. Changes in calibrated mass distribution of 99mTc at 30 s intervals, over a period of several hours, were quantified by spatial moments analysis. Transport parameters were fitted to the experimental data using a one-dimensional convection–dispersion equation, yielding transport properties for this radionuclide in a model GDF environment. These data demonstrate that 99Tc in the pertechnetate form (Tc(VII)O4–) does not sorb to cement backfill during transport under model conditions, resulting in closely conservative transport behavior. This methodology represents a quantitative development of radiotracer imaging and offers the opportunity to conveniently and rapidly characterize transport of gamma-emitting isotopes in opaque media, relevant to the geological disposal of nuclear waste and potentially to a wide variety of other subsurface environments. PMID:24147650

  4. Midwest Interstate Low-Level Radioactive Waste Commission annual report

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

    Not Available

    1988-08-01

    In 1980, Congress passed the Low-Level Radioactive Waste Policy Act. This Act provided for a new approach to the disposal of low-level radioactive waste. It assigned each state responsibility for the disposal of low-level radioactive waste generated within its borders, and it authorized states to enter into compacts for the purpose of operating regional disposal facilities. It also authorized compacts to restrict the use of regional disposal facilities to only member states. To meet their obligations under the Act, Indiana, Iowa, Michigan, Minnesota, Missouri, Ohio and Wisconsin formed the Midwest Interstate Low-Level Radioactive Waste Compact. The Compact was ratified bymore » each of the state legislatures and by Congress. The Compact established the Midwest Interstate Low-Level Radioactive Waste Commission, composed on one representative appointed by the Governor or Legislature of each member state. Article 3 of the compact requires that the Commission prepare an annual report regarding the activities and actions of the Commission. It also requires that the annual report be distributed to the Governors and legislative leaders in the member states. The Commission's Bylaw Article 12 requires the annual report to cover the preceding fiscal year, and to be distributed in August of each year. The Bylaw also requires that an annual audit, prepared by a certified public accountant, be included as part of the annual report. 3 figs.« less

  5. Corrective Action Decision Document/Closure Report for Corrective Action Unit 561: Waste Disposal Areas, Nevada National Security Site, Nevada, Revision 0

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

    Mark Krauss

    2011-08-01

    CAU 561 comprises 10 CASs: (1) 01-19-01, Waste Dump; (2) 02-08-02, Waste Dump and Burn Area; (3) 03-19-02, Debris Pile; (4) 05-62-01, Radioactive Gravel Pile; (5) 12-23-09, Radioactive Waste Dump; (6) 22-19-06, Buried Waste Disposal Site; (7) 23-21-04, Waste Disposal Trenches ; (8) 25-08-02, Waste Dump; (9) 25-23-21, Radioactive Waste Dump; and (10) 25-25-19, Hydrocarbon Stains and Trench. The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation for closure of CAU 561 with no further corrective action. The purpose of the CAI was to fulfill the following data needs as defined during the DQO process:more » (1) Determine whether COCs are present; (2) If COCs are present, determine their nature and extent; and (3) Provide sufficient information and data to complete appropriate corrective actions. The following contaminants were determined to be present at concentrations exceeding their corresponding FALs: (1) No contamination exceeding FALs was identified at CASs 01-19-01, 03-19-02, 05-62-01, 12-23-09, and 22-19-06. (2) The surface and subsurface soil within the burn area at CAS 02-08-02 contains arsenic and lead above the FALs of 23 milligrams per kilogram (mg/kg) and 800 mg/kg, respectively. The surface and subsurface soil within the burn area also contains melted lead slag (potential source material [PSM]). The soil within the waste piles contains polyaromatic hydrocarbons (PAHs) above the FALs. The contamination within the burn area is spread throughout the area, as it was not feasible to remove all the PSM (melted lead), while at the waste piles, the contamination is confined to the piles. (3) The surface and subsurface soils within Trenches 3 and 5 at CAS 23-21-04 contain arsenic and polychlorinated biphenyls (PCBs) above the FALs of 23 mg/kg and 0.74 mg/kg, respectively. The soil was removed from both trenches, and the soil that remains at this CAS does not contain contamination exceeding the FALs. Lead bricks and counterweights were also removed, and the soil below these items does not contain contamination that exceeds the FAL for lead. (4) The concrete-like material at CAS 25-08-02 contains arsenic above the FAL of 23 mg/kg. This concrete-like material was removed, and the soil that remains at this CAS does not contain contamination exceeding the FALs. Lead-acid batteries were also removed, and the soil below the batteries does not contain contamination that exceeds the FAL for lead. (5) The surface soils within the main waste dump at the posted southern radioactive material area (RMA) at CAS 25-23-21 contain cesium (Cs)-137 and PCBs above the FALs of 72.9 picocuries per gram (pCi/g) and 0.74 mg/kg, respectively. The soil was removed from the RMA, and the soil that remains at this CAS does not contain contamination exceeding the FALs. (6) The surface and subsurface soils at CAS 25-25-19 do not contain contamination exceeding the FALs. In addition, lead bricks were removed, and the soil below these items does not contain contamination that exceeds the FAL for lead. The following best management practices were implemented: (1) Housekeeping debris at CASs 02-08-02, 23-21-04, 25-08-02, 25-23-21, and 25-25-19 was removed and disposed of; (2) The open trenches at CAS 23-21-04 were backfilled; (3) The waste piles at CAS 25-08-02 were removed and the area leveled to ground surface; and (4) The remaining waste piles at the main waste dump at CAS 25-23-21 were leveled to ground surface. Therefore, NNSA/NSO provides the following recommendations: (1) No further action for CASs 01-19-01, 03-19-02, 05-62-01, 12-23-09, and 22-19-06; (2) Closure in place with an FFACO use restriction (UR) at CAS 02-08-02 for the remaining PAH-, arsenic-, and lead-contaminated soil, and the melted lead PSM. The UR form and map have been filed in the NNSA/NSO Facility Information Management System, the FFACO database, and the NNSA/NSO CAU/CAS files; (3) No further corrective action at CAS 23-21-04, as the lead bricks and counterweights (PSM) have been removed, and the COCs of arsenic and PCBs in soil have been removed; (4) No further corrective action at CAS 25-08-02, as the COC of arsenic in soil has been removed, and the lead-acid batteries have been removed; (5) No further corrective action at CAS 25-23-21, as the COCs of Cs-137 and PCBs in soil have been removed, and the cast-iron pipes have been removed and disposed of; (6) No further corrective action at CAS 25-25-19, as the lead bricks (PSM) been removed; (7) A Notice of Completion to the NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 561; and (8) Corrective Action Unit 561 should be moved from Appendix III to Appendix IV of the FFACO.« less

  6. Disposable rabbit

    DOEpatents

    Lewis, Leroy C.; Trammell, David R.

    1986-01-01

    A disposable rabbit for transferring radioactive samples in a pneumatic transfer system comprises aerated plastic shaped in such a manner as to hold a radioactive sample and aerated such that dissolution of the rabbit in a solvent followed by evaporation of the solid yields solid waste material having a volume significantly smaller than the original volume of the rabbit.

  7. Disposal rabbit

    DOEpatents

    Lewis, L.C.; Trammell, D.R.

    1983-10-12

    A disposable rabbit for transferring radioactive samples in a pneumatic transfer system comprises aerated plastic shaped in such a manner as to hold a radioactive sample and aerated such that dissolution of the rabbit in a solvent followed by evaporation of the solid yields solid waste material having a volume significantly smaller than the original volume of the rabbit.

  8. Biodegradation of the alkaline cellulose degradation products generated during radioactive waste disposal.

    PubMed

    Rout, Simon P; Radford, Jessica; Laws, Andrew P; Sweeney, Francis; Elmekawy, Ahmed; Gillie, Lisa J; Humphreys, Paul N

    2014-01-01

    The anoxic, alkaline hydrolysis of cellulosic materials generates a range of cellulose degradation products (CDP) including α and β forms of isosaccharinic acid (ISA) and is expected to occur in radioactive waste disposal sites receiving intermediate level radioactive wastes. The generation of ISA's is of particular relevance to the disposal of these wastes since they are able to form complexes with radioelements such as Pu enhancing their migration. This study demonstrates that microbial communities present in near-surface anoxic sediments are able to degrade CDP including both forms of ISA via iron reduction, sulphate reduction and methanogenesis, without any prior exposure to these substrates. No significant difference (n = 6, p = 0.118) in α and β ISA degradation rates were seen under either iron reducing, sulphate reducing or methanogenic conditions, giving an overall mean degradation rate of 4.7 × 10(-2) hr(-1) (SE ± 2.9 × 10(-3)). These results suggest that a radioactive waste disposal site is likely to be colonised by organisms able to degrade CDP and associated ISA's during the construction and operational phase of the facility.

  9. Bacterial Diversity in Bentonites, Engineered Barrier for Deep Geological Disposal of Radioactive Wastes.

    PubMed

    Lopez-Fernandez, Margarita; Cherkouk, Andrea; Vilchez-Vargas, Ramiro; Jauregui, Ruy; Pieper, Dietmar; Boon, Nico; Sanchez-Castro, Ivan; Merroun, Mohamed L

    2015-11-01

    The long-term disposal of radioactive wastes in a deep geological repository is the accepted international solution for the treatment and management of these special residues. The microbial community of the selected host rocks and engineered barriers for the deep geological repository may affect the performance and the safety of the radioactive waste disposal. In this work, the bacterial population of bentonite formations of Almeria (Spain), selected as a reference material for bentonite-engineered barriers in the disposal of radioactive wastes, was studied. 16S ribosomal RNA (rRNA) gene-based approaches were used to study the bacterial community of the bentonite samples by traditional clone libraries and Illumina sequencing. Using both techniques, the bacterial diversity analysis revealed similar results, with phylotypes belonging to 14 different bacterial phyla: Acidobacteria, Actinobacteria, Armatimonadetes, Bacteroidetes, Chloroflexi, Cyanobacteria, Deinococcus-Thermus, Firmicutes, Gemmatimonadetes, Planctomycetes, Proteobacteria, Nitrospirae, Verrucomicrobia and an unknown phylum. The dominant groups of the community were represented by Proteobacteria and Bacteroidetes. A high diversity was found in three of the studied samples. However, two samples were less diverse and dominated by Betaproteobacteria.

  10. Resource Management Plan for the US Department of Energy Oak Ridge Reservation. Volume 15, Appendix P: waste management

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

    Kelly, B.A.

    1984-07-01

    Since their inception, the DOE facilities on the Oak Ridge Reservation have been the source of a variety of airborne, liquid, and solid wastes which are characterized as nonhazardous, hazardous, and/or radioactive. The major airborne releases come from three primary sources: steam plant emissions, process discharge, and cooling towers. Liquid wastes are handled in various manners depending upon the particular waste, but in general, major corrosive waste streams are neutralized prior to discharge with the discharge routed to holding or settling ponds. The major solid wastes are derived from construction debris, sanitary operation, and radioactive processes, and the machining operationsmore » at Y-12. Nonradioactive hazardous wastes are disposed in solid waste storage areas, shipped to commercial disposal facilities, returned in sludge ponds, or sent to radioactive waste burial areas. The radioactive-hazardous wastes are treated in two manners: storage of the waste until acceptable disposal options are developed, or treatment of the waste to remove or destroy one of the components prior to disposal. 5 references, 4 figures, 13 tables.« less

  11. Modeling of transport phenomena in concrete porous media.

    PubMed

    Plecas, Ilija

    2014-02-01

    Two fundamental concerns must be addressed when attempting to isolate low-level waste in a disposal facility on land. The first concern is isolating the waste from water, or hydrologic isolation. The second is preventing movement of the radionuclides out of the disposal facility, or radionuclide migration. Particularly, we have investigated here the latter modified scenario. To assess the safety for disposal of radioactive waste-concrete composition, the leakage of 60Co from a waste composite into a surrounding fluid has been studied. Leakage tests were carried out by the original method, developed at the Vinča Institute. Transport phenomena involved in the leaching of a radioactive material from a cement composite matrix are investigated using three methods based on theoretical equations. These are: the diffusion equation for a plane source: an equation for diffusion coupled to a first-order equation, and an empirical method employing a polynomial equation. The results presented in this paper are from a 25-y mortar and concrete testing project that will influence the design choices for radioactive waste packaging for a future Serbian radioactive waste disposal center.

  12. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Waste Disposal Facility

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

    Ansley, Shannon Leigh

    2002-02-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering andmore » Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist.« less

  13. Impact of Scale-Dependent Coupled Processes on Solute Fate and Transport in the Critical Zone: Case Studies Involving Inorganic and Radioactive Contaminants

    NASA Astrophysics Data System (ADS)

    Jardine, P. M.; Gentry, R. W.

    2011-12-01

    Soil, the thin veneer of matter covering the Earths surface that supports a web of living diversity, is often abused through anthropogenic inputs of toxic waste. This subsurface regime, coupled with life sustaining surface water and groundwater is known as the "Critical Zone". The disposal of radioactive and toxic organic and inorganic waste generated by industry and various government agencies has historically involved shallow land burial or the use of surface impoundments in unsaturated soils and sediments. Presently, contaminated sites have been closing rapidly and many remediation strategies have chosen to leave contaminants in-place. As such, contaminants will continue to interact with the geosphere and investigations on long term changes and interactive processes is imperative to verify risks. In this presentation we provide a snap-shot of subsurface science research from the past 25 y that seeks to provide an improved understanding and predictive capability of multi-scale contaminant fate and transport processes in heterogeneous unsaturated and saturated environments. Investigations focus on coupled hydrological, geochemical, and microbial processes that control reactive contaminant transport and that involve multi-scale fundamental research ranging from the molecular scale (e.g. synchrotrons, electron sources, arrays) to in situ plume interrogation strategies at the macroscopic scale (e.g. geophysics, field biostimulation, coupled processes monitoring). We show how this fundamental research is used to provide multi-process, multi-scale predictive monitoring and modeling tools that can be used at contaminated sites to (1) inform and improve the technical basis for decision making, and (2) assess which sites are amenable to natural attenuation and which would benefit from source zone remedial intervention.

  14. 40 CFR 761.219 - One-year exception reporting.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... PROHIBITIONS PCB Waste Disposal Records and Reports § 761.219 One-year exception reporting. (a) A disposer of... affecting the facility's disposal capacity, the disposer of PCB waste could not dispose of the affected PCBs... PCB Items within 1 year from the date of removal from service for disposal. (d) PCB/radioactive waste...

  15. 40 CFR 761.219 - One-year exception reporting.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... PROHIBITIONS PCB Waste Disposal Records and Reports § 761.219 One-year exception reporting. (a) A disposer of... affecting the facility's disposal capacity, the disposer of PCB waste could not dispose of the affected PCBs... PCB Items within 1 year from the date of removal from service for disposal. (d) PCB/radioactive waste...

  16. Discussions about safety criteria and guidelines for radioactive waste management.

    PubMed

    Yamamoto, Masafumi

    2011-07-01

    In Japan, the clearance levels for uranium-bearing waste have been established by the Nuclear Safety Commission (NSC). The criteria for uranium-bearing waste disposal are also necessary; however, the NSC has not concluded the discussion on this subject. Meanwhile, the General Administrative Group of the Radiation Council has concluded the revision of its former recommendation 'Regulatory exemption dose for radioactive solid waste disposal', the dose criteria after the institutional control period for a repository. The Standardization Committee on Radiation Protection in the Japan Health Physics Society (The Committee) also has developed the relevant safety criteria and guidelines for existing exposure situations, which are potentially applicable to uranium-bearing waste disposal. A new working group established by The Committee was initially aimed at developing criteria and guidelines specifically for uranium-bearing waste disposal; however, the aim has been shifted to broader criteria applicable to any radioactive wastes.

  17. Corrosion behaviour of steel rebars embedded in a concrete designed for the construction of an intermediate-level radioactive waste disposal facility

    NASA Astrophysics Data System (ADS)

    Duffó, G. S.; Arva, E. A.; Schulz, F. M.; Vazquez, D. R.

    2013-07-01

    The National Atomic Energy Commission of the Argentine Republic is developing a nuclear waste disposal management programme that contemplates the design and construction of a facility for the final disposal of intermediate-level radioactive wastes. The repository is based on the use of multiple, independent and redundant barriers. The major components are made in reinforced concrete so, the durability of these structures is an important aspect for the facility integrity. This work presents an investigation performed on an instrumented reinforced concrete prototype specifically designed for this purpose, to study the behaviour of an intermediate level radioactive waste disposal facility from the rebar corrosion point of view. The information obtained will be used for the final design of the facility in order to guarantee a service life more or equal than the foreseen durability for this type of facilities.

  18. Durability of a reinforced concrete designed for the construction of an intermediate-level radioactive waste disposal facility

    NASA Astrophysics Data System (ADS)

    Duffó, G. S.; Arva, E. A.; Schulz, F. M.; Vazquez, D. R.

    2012-01-01

    The National Atomic Energy Commission of the Argentine Republic is developing a nuclear waste disposal management programme that contemplates the design and construction of a facility for the final disposal of intermediate-level radioactive wastes. The repository is based on the use of multiple, independent and redundant barriers. The major components are made in reinforced concrete so, the durability of these structures is an important aspect for the facility integrity. This work presents an investigation performed on a reinforced concrete specifically designed for this purpose, to predict the service life of the intermediate level radioactive waste disposal facility from data obtained with several techniques. Results obtained with corrosion sensors embedded in a concrete prototype are also included. The information obtained will be used for the final design of the facility in order to guarantee a service life more or equal than the foreseen durability for this type of facilities.

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

    Wyatt, Douglas

    Planning for ultimate Decontamination and Decommissioning (D and D) of a nuclear facility is as much a part of a successful nuclear strategy as is the ultimate disposal of radioactive waste. As facilities, in this case radioactive waste disposal trenches, are closed and abandoned leading to ultimate decommissioning, long term monitoring may be required. However, preplanning by characterizing, modeling, and monitoring the environment around the facility prior to and during operations will allow a performance assessment to be made and future behavior predicted. In the radioactive waste burial grounds of the Savannah River Site new slit trenches were constructed tomore » receive demolition debris associated with site foot print reduction. Some of the construction debris and associated process waste contained small amounts of tritium. Since the trenches were constructed over an existing tritium groundwater plume the monitoring and performance assessment of the trench, particularly with respect to tritium contributions to the vadose zone and groundwater, were important. These disposal trenches vary in length and width but are typically constructed within the upper 7 to 8 meters (21 to 24 feet) of the local sediments. The unconfined aquifer (water table) typically underlies the area at depths varying from 20 to 24 meters (60 to 72 feet), depending on elevation. Therefore, with downward flow and 13 to 16 meters (40 to 48 feet) of unsaturated sediments separating the base of the waste trenches from the unconfined aquifer, there was potential for an environmental impact to the sediments within the vadose zone and to the underlying groundwater. Monitoring and predicting this impact can support ultimate D and D activities and future performance assessment evaluation. From this work several key observations were made that will support long term monitoring and subsequent D and D: - The observed lateral variation of thinly bedded sands and clays may be less than 20 meters particularly if lenticular sands are present. Ultimate D and D should consider monitoring and remedial activities that consider sampling on scales to address this issue. - The detailed modeling, when compared with the modeled depositional patterns, indicates flow paths for vadose zone fluids, therefore a plan should allow for these flow paths. - Detailed lithostratigraphic modeling, when based on correlations between soil properties, CPT soundings and borehole geophysical logs, can aid in precision placement of subsurface sensors and sample points for performance monitoring and D and D assessment.« less

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

    Nichols, Will E.; Mehta, Sunil

    The updated Hanford Site Composite Analysis will provide an all-pathways dose projection to a hypothetical future member of the public from all planned low-level radioactive waste disposal facilities and potential contributions from all other projected end-state sources of radioactive material left at Hanford following site closure. Its primary purpose is to support the decision-making process of the U.S. Department of Energy (DOE) under DOE O 435.1-1, Radioactive Waste Management (DOE, 2001), related to managing low-level waste disposal facilities at the Hanford Site.

  1. Radioactively Contaminated Sites | RadTown USA | US EPA

    EPA Pesticide Factsheets

    2018-01-12

    If radioactive materials are used or disposed of improperly, they can contaminate buildings and the environment. Every site requiring cleanup is different depending on the type of facility, the radioactive elements involved and the concentration of the radioactive elements.

  2. The Impact of Solid Surface Features on Fluid-Fluid Interface Configuration

    NASA Astrophysics Data System (ADS)

    Araujo, J. B.; Brusseau, M. L. L.

    2017-12-01

    Pore-scale fluid processes in geological media are critical for a broad range of applications such as radioactive waste disposal, carbon sequestration, soil moisture distribution, subsurface pollution, land stability, and oil and gas recovery. The continued improvement of high-resolution image acquisition and processing have provided a means to test the usefulness of theoretical models developed to simulate pore-scale fluid processes, through the direct quantification of interfaces. High-resolution synchrotron X-ray microtomography is used in combination with advanced visualization tools to characterize fluid distributions in natural geologic media. The studies revealed the presence of fluid-fluid interface associated with macroscopic features on the surfaces of the solids such as pits and crevices. These features and respective fluid interfaces, which are not included in current theoretical or computational models, may have a significant impact on accurate simulation and understanding of multi-phase flow, energy, heat and mass transfer processes.

  3. SeSBench - An initiative to benchmark reactive transport models for environmental subsurface processes

    NASA Astrophysics Data System (ADS)

    Jacques, Diederik

    2017-04-01

    As soil functions are governed by a multitude of interacting hydrological, geochemical and biological processes, simulation tools coupling mathematical models for interacting processes are needed. Coupled reactive transport models are a typical example of such coupled tools mainly focusing on hydrological and geochemical coupling (see e.g. Steefel et al., 2015). Mathematical and numerical complexity for both the tool itself or of the specific conceptual model can increase rapidly. Therefore, numerical verification of such type of models is a prerequisite for guaranteeing reliability and confidence and qualifying simulation tools and approaches for any further model application. In 2011, a first SeSBench -Subsurface Environmental Simulation Benchmarking- workshop was held in Berkeley (USA) followed by four other ones. The objective is to benchmark subsurface environmental simulation models and methods with a current focus on reactive transport processes. The final outcome was a special issue in Computational Geosciences (2015, issue 3 - Reactive transport benchmarks for subsurface environmental simulation) with a collection of 11 benchmarks. Benchmarks, proposed by the participants of the workshops, should be relevant for environmental or geo-engineering applications; the latter were mostly related to radioactive waste disposal issues - excluding benchmarks defined for pure mathematical reasons. Another important feature is the tiered approach within a benchmark with the definition of a single principle problem and different sub problems. The latter typically benchmarked individual or simplified processes (e.g. inert solute transport, simplified geochemical conceptual model) or geometries (e.g. batch or one-dimensional, homogeneous). Finally, three codes should be involved into a benchmark. The SeSBench initiative contributes to confidence building for applying reactive transport codes. Furthermore, it illustrates the use of those type of models for different environmental and geo-engineering applications. SeSBench will organize new workshops to add new benchmarks in a new special issue. Steefel, C. I., et al. (2015). "Reactive transport codes for subsurface environmental simulation." Computational Geosciences 19: 445-478.

  4. 10 CFR 61.24 - Conditions of licenses.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61... waste may be disposed of until the Commission has inspected the land disposal facility and has found it... quantity of special nuclear material that has been disposed of. (j) The authority to dispose of wastes...

  5. 10 CFR 61.24 - Conditions of licenses.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61... waste may be disposed of until the Commission has inspected the land disposal facility and has found it... quantity of special nuclear material that has been disposed of. (j) The authority to dispose of wastes...

  6. 10 CFR 61.24 - Conditions of licenses.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61... waste may be disposed of until the Commission has inspected the land disposal facility and has found it... quantity of special nuclear material that has been disposed of. (j) The authority to dispose of wastes...

  7. 10 CFR 61.24 - Conditions of licenses.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61... waste may be disposed of until the Commission has inspected the land disposal facility and has found it... quantity of special nuclear material that has been disposed of. (j) The authority to dispose of wastes...

  8. 10 CFR 61.24 - Conditions of licenses.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61... waste may be disposed of until the Commission has inspected the land disposal facility and has found it... quantity of special nuclear material that has been disposed of. (j) The authority to dispose of wastes...

  9. 10 CFR 40.27 - General license for custody and long-term care of residual radioactive material disposal sites.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false General license for custody and long-term care of residual... residual radioactive material disposal sites. (a) A general license is issued for the custody of and long... water characterization and any necessary ground water protection activities or strategies. This...

  10. Canister arrangement for storing radioactive waste

    DOEpatents

    Lorenzo, D.K.; Van Cleve, J.E. Jr.

    1980-04-23

    The subject invention relates to a canister arrangement for jointly storing high level radioactive chemical waste and metallic waste resulting from the reprocessing of nuclear reactor fuel elements. A cylindrical steel canister is provided with an elongated centrally disposed billet of the metallic waste and the chemical waste in vitreous form is disposed in the annulus surrounding the billet.

  11. Canister arrangement for storing radioactive waste

    DOEpatents

    Lorenzo, Donald K.; Van Cleve, Jr., John E.

    1982-01-01

    The subject invention relates to a canister arrangement for jointly storing high level radioactive chemical waste and metallic waste resulting from the reprocessing of nuclear reactor fuel elements. A cylindrical steel canister is provided with an elongated centrally disposed billet of the metallic waste and the chemical waste in vitreous form is disposed in the annulus surrounding the billet.

  12. U.S. Geological Survey research in radioactive waste disposal - Fiscal years 1983, 1984, and 1985

    USGS Publications Warehouse

    Dinwiddie, G.A.; Trask, N.J.

    1986-01-01

    The report summarizes progress on geologic and hydrologic research related to the disposal of radioactive wastes. The research is described according to whether it is related most directly to: (1) high-level and transuranic wastes, (2) low-level wastes, or (3) uranium mill tailings. Included is research applicable to the identification and geohydrologic characterization of waste-disposal sites, to investigations of specific sites where wastes have been stored, and to studies of regions or environments where waste-disposal sites might be located. A significant part of the activity is concerned with techniques and methods for characterizing disposal sites and studies of geologic and hydrologic processes related to the transport and (or) retention of waste radionuclides.

  13. U.S. Geological Survey research in radioactive waste disposal - Fiscal years 1986-1990

    USGS Publications Warehouse

    Trask, N.J.; Stevens, P.R.

    1991-01-01

    The report summarizes progress on geologic and hydrologic research related to the disposal of radioactive wastes. The research efforts are categorized according to whether they are related most directly to: (1) high-level wastes, (2) transuranic wastes, (3) low-level and mixed low-level and hazardous wastes, or (4) uranium mill tailings. Included is research applicable to the identification and geohydrologic characterization of waste-disposal sites, to investigations of specific sites where wastes have been stored, to development of techniques and methods for characterizing disposal sites, and to studies of geologic and hydrologic processes related to the transport and/or retention of waste radionuclides.

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

    Cochran, John Russell

    The Al Tuwaitha nuclear complex near Baghdad contains a number of facilities from Saddam Hussan's nuclear weapons program. Past military operations, lack of upkeep and looting have created an enormous radioactive waste problem at the Al Tuwaitha complex, which contains various, uncharacterized radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals that must be constantly guarded. Iraq has never had a radioactive waste disposal facility and the lack of a disposal facility means that ever increasing quantities of radioactive material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has beenmore » initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS is funding the IAEA to provide technical assistance via Technical Cooperation projects. Program coordination will be provided by the DOS, consistent with GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for implementation of the NDs Program.« less

  15. Treatment of Radioactive Metallic Waste from Operation of Nuclear Power Plants by Melting - The German Way for a Consistent Recycling to Minimize the Quantity of Radioactive Waste from Operation and Dismantling for Disposal - 12016

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

    Wegener, Dirk; Kluth, Thomas

    2012-07-01

    During maintenance of nuclear power plants, and during their decommissioning period, a large quantity of radioactive metallic waste will accrue. On the other hand the capacity for final disposal of radioactive waste in Germany is limited as well as that in the US. That is why all procedures related to this topic should be handled with a maximum of efficiency. The German model of consistent recycling of the radioactive metal scrap within the nuclear industry therefore also offers high capabilities for facilities in the US. The paper gives a compact overview of the impressive results of melting treatment, the currentmore » potential and further developments. Thousands of cubic metres of final disposal capacity have been saved. The highest level of efficiency and safety by combining general surface decontamination by blasting and nuclide specific decontamination by melting associated with the typical effects of homogenization. An established process - nationally and internationally recognized. Excellent connection between economy and ecology. (authors)« less

  16. 10 CFR 61.44 - Stability of the disposal site after closure.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Stability of the disposal site after closure. 61.44 Section 61.44 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.44 Stability of the disposal site after closure. The disposal...

  17. 10 CFR 61.44 - Stability of the disposal site after closure.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Stability of the disposal site after closure. 61.44 Section 61.44 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.44 Stability of the disposal site after closure. The disposal...

  18. 10 CFR 61.44 - Stability of the disposal site after closure.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Stability of the disposal site after closure. 61.44 Section 61.44 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.44 Stability of the disposal site after closure. The disposal...

  19. 10 CFR 61.44 - Stability of the disposal site after closure.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Stability of the disposal site after closure. 61.44 Section 61.44 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.44 Stability of the disposal site after closure. The disposal...

  20. 10 CFR 61.44 - Stability of the disposal site after closure.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Stability of the disposal site after closure. 61.44 Section 61.44 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.44 Stability of the disposal site after closure. The disposal...

  1. Ground-water hydrology and subsurface migration of radioisotopes at a low-level solid radioactive-waste disposal site, West Valley, New York

    USGS Publications Warehouse

    Prudic, David E.; Randall, Allan D.

    1977-01-01

    Burial trenches for disposal of solid radioactive waste at West Valley, N.Y., are excavated in till that has very low hydraulic conductivity (about 5 x 10 to the minus 8th power centimeters per second). Fractures and root tubes with chemically oxidized and (or) reduced soil in their walls extend to 3 to 4.5 meters below natural land surface. Preliminary simulations of pressure heads with a digital model suggest that hydraulic conductivity is an order of magnitude greater in the fractured till near land surface than at greater depth. Hydraulic gradients are predominantly downward, even beneath small valleys. The upper part of a body of underlying lacustrine silt is unsaturated; in the lower, saturated part, slow lateral flow may occur. In the older trenches, water began to build up in 1971, overflowed briefly in 1975, and was pumped out in 1975-76. Water levels rose abruptly during major rainstorms in mid-1975, indicating rapid infiltration through cracks in the cover material. The new trenches have maintained low, stable water levels, perhaps because of thicker, more compact cover and less waste settlement; pressure heads near these trenches are low, locally approaching zero, perhaps because of slight infiltration and limited near-surface storage. Peak tritium concentrations in test-hole cores (generally 0.00001 to 0.001 microcuries per milliliter) were found within 3 meters of land surface and are attributed to surface contamination. Concentrations declined rapidly with depth within the fractured till; secondary peaks found at about 9 meters in three holes are attributed to lateral migration from trenches. Other radioisotopes were detected only near land surface. Samples from the walls of shallow fractures revealed no accumulation of radioisotopes. (Woodard-USGS)

  2. 10 CFR 61.62 - Funding for disposal site closure and stabilization.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... Section 61.62 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Financial Assurances § 61.62 Funding for disposal site closure and stabilization. (a) The... and stabilization, including: (1) Decontamination or dismantlement of land disposal facility...

  3. 10 CFR 61.62 - Funding for disposal site closure and stabilization.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... Section 61.62 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Financial Assurances § 61.62 Funding for disposal site closure and stabilization. (a) The... and stabilization, including: (1) Decontamination or dismantlement of land disposal facility...

  4. 10 CFR 61.62 - Funding for disposal site closure and stabilization.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... Section 61.62 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Financial Assurances § 61.62 Funding for disposal site closure and stabilization. (a) The... and stabilization, including: (1) Decontamination or dismantlement of land disposal facility...

  5. 10 CFR 61.62 - Funding for disposal site closure and stabilization.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... Section 61.62 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Financial Assurances § 61.62 Funding for disposal site closure and stabilization. (a) The... and stabilization, including: (1) Decontamination or dismantlement of land disposal facility...

  6. 10 CFR 61.62 - Funding for disposal site closure and stabilization.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... Section 61.62 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Financial Assurances § 61.62 Funding for disposal site closure and stabilization. (a) The... and stabilization, including: (1) Decontamination or dismantlement of land disposal facility...

  7. GEOTHERMAL ENVIRONMENTAL IMPACT ASSESSMENT: SUBSURFACE ENVIRONMENTAL ASSESSMENT FOR FOUR GEOTHERMAL SYSTEMS

    EPA Science Inventory

    This is the second in a series of reports concerning the environmental assessments of effluent extraction, energy conversion, and waste disposal in geothermal systems. This study involves the subsurface environmental impact of the Imperial Valley and The Geysers, California; Klam...

  8. Characterization of Class A low-level radioactive waste 1986--1990. Volume 6: Appendices G--J

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

    Dehmel, J.C.; Loomis, D.; Mauro, J.

    1994-01-01

    Under contract to the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, the firms of S. Cohen & Associates, Inc. (SC&A) and Eastern Research Group (ERG) have compiled a report that describes the physical, chemical, and radiological properties of Class-A low-level radioactive waste. The report also presents information characterizing various methods and facilities used to treat and dispose non-radioactive waste. A database management program was developed for use in accessing, sorting, analyzing, and displaying the electronic data provided by EG&G. The program was used to present and aggregate data characterizing the radiological, physical, and chemical properties of the wastemore » from descriptions contained in shipping manifests. The data thus retrieved are summarized in tables, histograms, and cumulative distribution curves presenting radionuclide concentration distributions in Class-A waste as a function of waste streams, by category of waste generators, and regions of the United States. The report also provides information characterizing methods and facilities used to treat and dispose non-radioactive waste, including industrial, municipal, and hazardous waste regulated under Subparts C and D of the Resource Conservation and Recovery Act (RCRA). The information includes a list of disposal options, the geographical locations of the processing and disposal facilities, and a description of the characteristics of such processing and disposal facilities. Volume 1 contains the Executive Summary, Volume 2 presents the Class-A waste database, Volume 3 presents the information characterizing non-radioactive waste management practices and facilities, and Volumes 4 through 7 contain Appendices A through P with supporting information.« less

  9. NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA, JUNE 2006

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

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

  10. Nevada Test Site Waste Acceptance Criteria

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

    U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

  11. Decision Support System For Management Of Low-Level Radioactive Waste Disposal At The Nevada Test Site

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

    Shott, G.; Yucel, V.; Desotell, L.

    2006-07-01

    The long-term safety of U.S. Department of Energy (DOE) low-level radioactive disposal facilities is assessed by conducting a performance assessment -- a systematic analysis that compares estimated risks to the public and the environment with performance objectives contained in DOE Manual 435.1-1, Radioactive Waste Management Manual. Before site operations, facilities design features such as final inventory, waste form characteristics, and closure cover design may be uncertain. Site operators need a modeling tool that can be used throughout the operational life of the disposal site to guide decisions regarding the acceptance of problematic waste streams, new disposal cell design, environmental monitoringmore » program design, and final site closure. In response to these needs the National Nuclear Security Administration Nevada Site Office (NNSA/NSO) has developed a decision support system for the Area 5 Radioactive Waste Management Site in Frenchman Flat on the Nevada Test Site. The core of the system is a probabilistic inventory and performance assessment model implemented in the GoldSim{sup R} simulation platform. The modeling platform supports multiple graphic capabilities that allow clear documentation of the model data sources, conceptual model, mathematical implementation, and results. The combined models have the capability to estimate disposal site inventory, contaminant concentrations in environmental media, and radiological doses to members of the public engaged in various activities at multiple locations. The model allows rapid assessment and documentation of the consequences of waste management decisions using the most current site characterization information, radionuclide inventory, and conceptual model. The model is routinely used to provide annual updates of site performance, evaluate the consequences of disposal of new waste streams, develop waste concentration limits, optimize the design of new disposal cells, and assess the adequacy of environmental monitoring programs. (authors)« less

  12. Radioactive waste storage issues

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

    Kunz, Daniel E.

    1994-08-15

    In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal)more » of wastes generated solely within a state`s boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected.« less

  13. Study of extraterrestrial disposal of radioactive wastes. Part 3: Preliminary feasibility screening study of space disposal of the actinide radioactive wastes with 1 percent and 0.1 percent fission product contamination

    NASA Technical Reports Server (NTRS)

    Hyland, R. E.; Wohl, M. L.; Finnegan, P. M.

    1973-01-01

    A preliminary study was conducted of the feasibility of space disposal of the actinide class of radioactive waste material. This waste was assumed to contain 1 and 0.1 percent residual fission products, since it may not be feasible to completely separate the actinides. The actinides are a small fraction of the total waste but they remain radioactive much longer than the other wastes and must be isolated from human encounter for tens of thousands of years. Results indicate that space disposal is promising but more study is required, particularly in the area of safety. The minimum cost of space transportation would increase the consumer electric utility bill by the order of 1 percent for earth escape and 3 percent for solar escape. The waste package in this phase of the study was designed for normal operating conditions only; the design of next phase of the study will include provisions for accident safety. The number of shuttle launches per year required to dispose of all U.S. generated actinide waste with 0.1 percent residual fission products varies between 3 and 15 in 1985 and between 25 and 110 by 2000. The lower values assume earth escape (solar orbit) and the higher values are for escape from the solar system.

  14. Marine Electromagnetic System Development in the Shallow Water Environment for Radioactive Waste Repository Site Investigation

    NASA Astrophysics Data System (ADS)

    Yoshimura, K.; Sakashita, S.; Okubo, S.; Yamane, K.

    2006-12-01

    Radioactive Waste Management Funding and Research Center of Japan has recently conducted a program to develop an electromagnetic (EM) technology for investigating the subsurface to the depths of 1,000m below the seafloor in the near-shore environment. Potential applications include structural studies for geological disposal of radioactive wastes. The system includes both natural field by magnetotellurics and controlled source EM data was collected to evaluate the feasibility of the methods and instrumentation. The shallow water environment is challenging because of high water currents and wave motion effects contaminating the data. We demonstrate the performance test of the new type of instrument, and the field experiment that was carried out in the Monterey Bay of California, USA, in 2003 and 2004. In this paper we describe the instrumentation developed, shows some examples from field trial and finally provide some inversion results using collected and simulated data. The system consists of EM transmitter deployed on the beach in combination with a series of offshore based multicomponent receivers. Field data collected near Monterey California revealed some of the challenges associated with this type of system. Collected data showed the influence of wave and cultural noise as well. In site of these difficulties we were able to accumulate a sufficient quantity of good quality records to interpret results. We show 2-D inversion results which image the "Navy Fault zone" which strikes NW-SE offshore Monterey bay in water depths of 10 to 40m.

  15. Preliminary Comparison of Radioactive Waste Disposal Cost for Fusion and Fission Reactors

    NASA Astrophysics Data System (ADS)

    Seki, Yasushi; Aoki, Isao; Yamano, Naoki; Tabara, Takashi

    1997-09-01

    The environmental and economic impact of radioactive waste (radwaste) generated from fusion power reactors using five types of structural materials and a fission reactor has been evaluated and compared. Possible radwaste disposal scenario of fusion radwaste in Japan is considered. The exposure doses were evaluated for the skyshine of gamma-ray during the disposal operation, groundwater migration scenario during the institutional control period of 300 years and future site use scenario after the institutional period. The radwaste generated from a typical light water fission reactor was evaluated using the same methodology as for the fusion reactors. It is found that radwaste from the fusion reactors using F82H and SiC/SiC composites without impurities could be disposed by the shallow land disposal presently applied to the low level waste in Japan. The disposal cost of radwaste from five fusion power reactors and a typical light water reactor were roughly evaluated and compared.

  16. Radiocarbon signal of a low and intermediate level radioactive waste disposal facility in nearby trees.

    PubMed

    Janovics, R; Kelemen, D I; Kern, Z; Kapitány, S; Veres, M; Jull, A J T; Molnár, M

    2016-03-01

    Tree ring series were collected from the vicinity of a Hungarian radioactive waste treatment and disposal facility and from a distant control background site, which is not influenced by the radiocarbon discharge of the disposal facility but it represents the natural regional (14)C level. The (14)C concentration of the cellulose content of tree rings was measured by AMS. Data of the tree ring series from the disposal facility was compared to the control site for each year. The results were also compared to the (14)C data of the atmospheric (14)C monitoring stations at the disposal facility and to international background measurements. On the basis of the results, the excess radiocarbon of the disposal facility can unambiguously be detected in the tree from the repository site. Copyright © 2016 Elsevier Ltd. All rights reserved.

  17. 40 CFR 268.36 - Waste specific prohibitions-inorganic chemical wastes

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ...) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS Prohibitions on Land Disposal § 268.36 Waste... radioactive wastes mixed with these wastes are prohibited from land disposal. (b) The requirements of... applicable subpart D levels, the waste is prohibited from land disposal, and all requirements of this part...

  18. 40 CFR 268.35 - Waste specific prohibitions-petroleum refining wastes.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ...) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS Prohibitions on Land Disposal § 268.35 Waste... contaminated with these radioactive mixed wastes, are prohibited from land disposal. (b) The requirements of... Universal Treatment Standard levels of § 268.48, the waste is prohibited from land disposal, and all...

  19. 40 CFR 268.35 - Waste specific prohibitions-petroleum refining wastes.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ...) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS Prohibitions on Land Disposal § 268.35 Waste... contaminated with these radioactive mixed wastes, are prohibited from land disposal. (b) The requirements of... Universal Treatment Standard levels of § 268.48, the waste is prohibited from land disposal, and all...

  20. 10 CFR 61.82 - Commission inspections of land disposal facilities.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Commission inspections of land disposal facilities. 61.82 Section 61.82 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Records, Reports, Tests, and Inspections § 61.82 Commission inspections of land disposal...

  1. 40 CFR 268.35 - Waste specific prohibitions-petroleum refining wastes.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ...) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS Prohibitions on Land Disposal § 268.35 Waste... contaminated with these radioactive mixed wastes, are prohibited from land disposal. (b) The requirements of... Universal Treatment Standard levels of § 268.48, the waste is prohibited from land disposal, and all...

  2. 40 CFR 268.36 - Waste specific prohibitions-inorganic chemical wastes

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ...) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS Prohibitions on Land Disposal § 268.36 Waste... radioactive wastes mixed with these wastes are prohibited from land disposal. (b) The requirements of... applicable subpart D levels, the waste is prohibited from land disposal, and all requirements of this part...

  3. 40 CFR 268.36 - Waste specific prohibitions-inorganic chemical wastes

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ...) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS Prohibitions on Land Disposal § 268.36 Waste... radioactive wastes mixed with these wastes are prohibited from land disposal. (b) The requirements of... applicable subpart D levels, the waste is prohibited from land disposal, and all requirements of this part...

  4. 40 CFR 268.36 - Waste specific prohibitions-inorganic chemical wastes.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ...) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS Prohibitions on Land Disposal § 268.36 Waste... radioactive wastes mixed with these wastes are prohibited from land disposal. (b) The requirements of... applicable subpart D levels, the waste is prohibited from land disposal, and all requirements of this part...

  5. 40 CFR 268.35 - Waste specific prohibitions-petroleum refining wastes.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ...) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS Prohibitions on Land Disposal § 268.35 Waste... contaminated with these radioactive mixed wastes, are prohibited from land disposal. (b) The requirements of... Universal Treatment Standard levels of § 268.48, the waste is prohibited from land disposal, and all...

  6. 10 CFR 61.81 - Tests at land disposal facilities.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Tests at land disposal facilities. 61.81 Section 61.81 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Records, Reports, Tests, and Inspections § 61.81 Tests at land disposal facilities. (a) Each...

  7. 10 CFR 61.82 - Commission inspections of land disposal facilities.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Commission inspections of land disposal facilities. 61.82 Section 61.82 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Records, Reports, Tests, and Inspections § 61.82 Commission inspections of land disposal...

  8. 10 CFR 61.81 - Tests at land disposal facilities.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Tests at land disposal facilities. 61.81 Section 61.81 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Records, Reports, Tests, and Inspections § 61.81 Tests at land disposal facilities. (a) Each...

  9. 10 CFR 61.82 - Commission inspections of land disposal facilities.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Commission inspections of land disposal facilities. 61.82 Section 61.82 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Records, Reports, Tests, and Inspections § 61.82 Commission inspections of land disposal...

  10. 40 CFR 268.36 - Waste specific prohibitions-inorganic chemical wastes.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ...) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS Prohibitions on Land Disposal § 268.36 Waste... radioactive wastes mixed with these wastes are prohibited from land disposal. (b) The requirements of... applicable subpart D levels, the waste is prohibited from land disposal, and all requirements of this part...

  11. 10 CFR 61.81 - Tests at land disposal facilities.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Tests at land disposal facilities. 61.81 Section 61.81 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Records, Reports, Tests, and Inspections § 61.81 Tests at land disposal facilities. (a) Each...

  12. 40 CFR 268.35 - Waste specific prohibitions-petroleum refining wastes.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ...) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS Prohibitions on Land Disposal § 268.35 Waste... contaminated with these radioactive mixed wastes, are prohibited from land disposal. (b) The requirements of... Universal Treatment Standard levels of § 268.48, the waste is prohibited from land disposal, and all...

  13. 41 CFR 50-204.29 - Waste disposal.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 41 Public Contracts and Property Management 1 2010-07-01 2010-07-01 true Waste disposal. 50-204.29 Section 50-204.29 Public Contracts and Property Management Other Provisions Relating to Public Contracts... Radiation Standards § 50-204.29 Waste disposal. No employer shall dispose of radioactive material except by...

  14. Considerations Related To Human Intrusion In The Context Of Disposal Of Radioactive Waste-The IAEA HIDRA Project

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

    Seitz, Roger; Kumano, Yumiko; Bailey, Lucy

    2014-01-09

    The principal approaches for management of radioactive waste are commonly termed ‘delay and decay’, ‘concentrate and contain’ and ‘dilute and disperse’. Containing the waste and isolating it from the human environment, by burying it, is considered to increase safety and is generally accepted as the preferred approach for managing radioactive waste. However, this approach results in concentrated sources of radioactive waste contained in one location, which can pose hazards should the facility be disrupted by human action in the future. The International Commission on Radiological Protection (ICRP), International Atomic Energy Agency (IAEA), and Organization for Economic Cooperation and Development/Nuclear Energymore » Agency (OECD/NEA) agree that some form of inadvertent human intrusion (HI) needs to be considered to address the potential consequences in the case of loss of institutional control and loss of memory of the disposal facility. Requirements are reflected in national regulations governing radioactive waste disposal. However, in practice, these requirements are often different from country to country, which is then reflected in the actual implementation of HI as part of a safety case. The IAEA project on HI in the context of Disposal of RadioActive waste (HIDRA) has been started to identify potential areas for improved consistency in consideration of HI. The expected outcome is to provide recommendations on how to address human actions in the safety case in the future, and how the safety case may be used to demonstrate robustness and optimize siting, design and waste acceptance criteria within the context of a safety case.« less

  15. 1st Quarter Transportation Report FY 2015: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

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

    Gregory, Louis

    2015-02-20

    This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to and from the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the 1st quarter of Fiscal Year (FY) 2015 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. Tabular summaries are provided which include the following: Sources of and carriers for LLW and MLLW shipments tomore » and from the NNSS; Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report include minor volumes of non-radioactive classified waste/material that were approved for disposal (non-radioactive classified or nonradioactive classified hazardous). Volume reports showing cubic feet generated using the Low-Level Waste Information System may vary slightly due to rounding conventions for volumetric conversions from cubic meters to cubic feet.« less

  16. Dancing with the regulations - Part Deux

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

    Nitschke, R.L.

    1995-12-31

    The disposal of low-level radioactive waste (LLW) in the United States has long been subjected to two very similar regulations depending upon the location. Disposal sites located on Department of Energy (DOE) Reservations are subject to DOE Order 5820.2A {open_quotes}Radioactive Waste Management,{close_quotes} while disposal sites located elsewhere are subject to the Nuclear Regulatory Commission regulation 10 CFR 61 {open_quotes}Licensing Requirements for Land Disposal of Radioactive Waste.{close_quotes} While life was not necessarily good, there was only one sheet of music to dance to. Recently a new player, named CERCLA (Comprehensive Environmental Response, Compensation, and Liability Act), has ridden into those DOEmore » towns, and for those whose disposal facilities lie within or adjacent to Superfund sites, she has brought along a different drum to dance to. This paper discusses the differences and similarities between the different dance partners and their associated musical scores (i.e., the performance assessment (PA) required by the DOE order and the baseline risk assessment (BRA) required by CERCLA). The paper then provides a brief discussion on the latest dancer to cut in: the Defense Nuclear Facilities Safety Board (DNFSB). This discussion should help to alleviate the confusion while dancing on the LLW disposal regulatory ballroom floor.« less

  17. Final environmental impact statement. Management of commercially generated radioactive waste. Volume 3. Public comments hearing board report

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

    Not Available

    1980-10-01

    This EIS analyzes the significant environmental impacts that could occur if various technologies for management and disposal of high-level and transuranic wastes from commercial nuclear power reactors were to be developed and implemented. This EIS will serve as the environmental input for the decision on which technology, or technologies, will be emphasized in further research and development activities in the commercial waste management program. The action proposed in this EIS is to (1) adopt a national strategy to develop mined geologic repositories for disposal of commercially generated high-level and transuranic radioactive waste (while continuing to examine subseabed and very deepmore » hole disposal as potential backup technologies) and (2) conduct a R and D program to develop such facilities and the necessary technology to ensure the safe long-term containment and isolation of these wastes. The Department has considered in this statement: development of conventionally mined deep geologic repositories for disposal of spent fuel from nuclear power reactors and/or radioactive fuel reprocessing wastes; balanced development of several alternative disposal methods; and no waste disposal action. This volume contains written public comments and hearing board responses and reports offered on the draft statement.« less

  18. Superfund Policy Statements and Guidance Regarding Disposition of Radioactive Waste in Non-NRC Licensed Disposal Facilities - 13407

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

    Walker, Stuart

    2013-07-01

    This talk will discuss EPA congressional testimony and follow-up letters, as well as letters to other stakeholders on EPA's perspectives on the disposition of radioactive waste outside of the NRC licensed disposal facility system. This will also look at Superfund's historical practices, and emerging trends in the NRC and agreement states on waste disposition. (author)

  19. LANL OPERATING EXPERIENCE WITH THE WAND AND HERCULES PROTOTYPE SYSTEMS

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

    K. M. GRUETZMACHER; C. L. FOXX; S. C. MYERS

    2000-09-01

    The Waste Assay for Nonradioactive Disposal (WAND) and the High Efficiency Radiation Counters for Ultimate Low Emission Sensitivity (HERCULES) prototype systems have been operating at Los Alamos National Laboratory's (LANL's) Solid Waste Operation's (SWO'S) non-destructive assay (NDA) building since 1997 and 1998, respectively. These systems are the cornerstone of the verification program for low-density Green is Clean (GIC) waste at the Laboratory. GIC waste includes all non-regulated waste generated in radiological controlled areas (RCAS) that has been actively segregated as clean (i.e., nonradioactive) through the use of waste generator acceptable knowledge (AK). The use of this methodology alters LANL's pastmore » practice of disposing of all room trash generated in nuclear facilities in radioactive waste landfills. Waste that is verified clean can be disposed of at the Los Alamos County Landfill. It is estimated that 50-90% of the low-density room trash from radioactive material handling areas at Los Alamos might be free of contamination. This approach avoids the high cost of disposal of clean waste at a radioactive waste landfill. It also reduces consumption of precious space in the radioactive waste landfill where disposal of this waste provides no benefit to the public or the environment. Preserving low level waste (LLW) disposal capacity for truly radioactive waste is critical in this era when expanding existing radioactive waste landfills or permitting new ones is resisted by regulators and stakeholders. This paper describes the operating experience with the WAND and HERCULES since they began operation at SWO. Waste for verification by the WAND system has been limited so far to waste from the Plutonium Facility and the Solid Waste Operations Facility. A total of461 ft3 (13.1 m3) of low-density shredded waste and paper have been verified clean by the WAND system. The HERCULES system has been used to verify waste from four Laboratory facilities. These are the Solid Waste Operations Facility, the TA-48 Chemistry Facility, the Shops Facility, and the Environmental Facility. A total of 3150 ft3 (89.3 m3) of low-density waste has been verified clean by the HERCULES system.« less

  20. International Approaches for Nuclear Waste Disposal in Geological Formations: Report on Fifth Worldwide Review

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

    Faybishenko, Boris; Birkholzer, Jens; Persoff, Peter

    2016-08-01

    An important issue for present and future generations is the final disposal of spent nuclear fuel. Over the past over forty years, the development of technologies to isolate both spent nuclear fuel (SNF) and other high-level nuclear waste (HLW) generated at nuclear power plants and from production of defense materials, and low- and intermediate-level nuclear waste (LILW) in underground rock and sediments has been found to be a challenging undertaking. Finding an appropriate solution for the disposal of nuclear waste is an important issue for protection of the environment and public health, and it is a prerequisite for the futuremore » of nuclear power. The purpose of a deep geological repository for nuclear waste is to provide to future generations, protection against any harmful release of radioactive material, even after the memory of the repository may have been lost, and regardless of the technical knowledge of future generations. The results of a wide variety of investigations on the development of technology for radioactive waste isolation from 19 countries were published in the First Worldwide Review in 1991 (Witherspoon, 1991). The results of investigations from 26 countries were published in the Second Worldwide Review in 1996 (Witherspoon, 1996). The results from 32 countries were summarized in the Third Worldwide Review in 2001 (Witherspoon and Bodvarsson, 2001). The last compilation had results from 24 countries assembled in the Fourth Worldwide Review (WWR) on radioactive waste isolation (Witherspoon and Bodvarsson, 2006). Since publication of the last report in 2006, radioactive waste disposal approaches have continued to evolve, and there have been major developments in a number of national geological disposal programs. Significant experience has been obtained both in preparing and reviewing cases for the operational and long-term safety of proposed and operating repositories. Disposal of radioactive waste is a complex issue, not only because of the nature of the waste, but also because of the detailed regulatory structure for dealing with radioactive waste, the variety of stakeholders involved, and (in some cases) the number of regulatory entities involved.« less

  1. Resistivity profiling for mapping gravel layers that may control contaminant migration at the Amargosa Desert Research Site, Nevada

    USGS Publications Warehouse

    Lucius, Jeffrey E.; Abraham, Jared D.; Burton, Bethany L.

    2008-01-01

    Gaseous contaminants, including CFC 113, chloroform, and tritiated compounds, move preferentially in unsaturated subsurface gravel layers away from disposal trenches at a closed low-level radioactive waste-disposal facility in the Amargosa Desert about 17 kilometers south of Beatty, Nevada. Two distinct gravel layers are involved in contaminant transport: a thin, shallow layer between about 0.5 and 2.2 meters below the surface and a layer of variable thickness between about 15 and 30 meters below land surface. From 2003 to 2005, the U.S. Geological Survey used multielectrode DC and AC resistivity surveys to map these gravel layers. Previous core sampling indicates the fine-grained sediments generally have higher water content than the gravel layers or the sediments near the surface. The relatively higher electrical resistivity of the dry gravel layers, compared to that of the surrounding finer sediments, makes the gravel readily mappable using electrical resistivity profiling. The upper gravel layer is not easily distinguished from the very dry, fine-grained deposits at the surface. Two-dimensional resistivity models, however, clearly identify the resistive lower gravel layer, which is continuous near the facility except to the southeast. Multielectrode resistivity surveys provide a practical noninvasive method to image hydrogeologic features in the arid environment of the Amargosa Desert.

  2. 10 CFR 20.1501 - General.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... COMMISSION STANDARDS FOR PROTECTION AGAINST RADIATION Surveys and Monitoring § 20.1501 General. (a) Each licensee shall make or cause to be made, surveys of areas, including the subsurface, that— (1) May be... surveys describing the location and amount of subsurface residual radioactivity identified at the site...

  3. 10 CFR 20.1501 - General.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... COMMISSION STANDARDS FOR PROTECTION AGAINST RADIATION Surveys and Monitoring § 20.1501 General. (a) Each licensee shall make or cause to be made, surveys of areas, including the subsurface, that— (1) May be... surveys describing the location and amount of subsurface residual radioactivity identified at the site...

  4. Ground-water flow near two radioactive-waste-disposal areas at the Western New York Nuclear Service Center, Cattaraugus County, New York; results of flow simulation

    USGS Publications Warehouse

    Bergeron, M.P.; Bugliosi, E.F.

    1988-01-01

    Two adjacent burial areas were excavated in a clay-rich till at a radioactive waste disposal site near West Valley in Cattaraugus County, N.Y.: (1) which contains mainly low-level radioactive wastes generated onsite by a nuclear fuel reprocessing plant, has been in operation since 1966; and (2) which contains commercial low-level radioactive wastes, was operated during 1963-75. Groundwater below the upper 3 meters of till generally moves downward through a 20- to 30-meter thick sequence of tills underlain by lacustrine and kame-delta deposits of fine sand and silt. Groundwater in the weathered, upper 3 meters of till can move laterally for several meters before either moving downward into the kame-delta deposits or discharging to the land surface. A two-dimensional finite-element model that simulates two vertical sections was used to evaluate hydrologic factors that control groundwater flow in the till. Conditions observed during March 1983 were reproduced accurately in steady-state simulations that used four isotropic units of differing hydraulic conductivity to represent two fractured and weathered till units near land surfaces, an intermediate group of isolated till zones that contain significant amounts of fine sand and silt, and a sequence of till units at depths that have been consolidated by overburden pressure. Recharge rates used in the best-fit simulation ranged from 1.4 cm/yr along smooth, sloping or compacted surfaces to 3.8 cm/yr near swampy areas. Values of hydraulic conductivity and infiltration used in the calibrated best-fit model were nearly identical to values used in a previous model analysis of the nearby commercial-waste burial area. Results of the model simulations of a burial pit assumed to be filled with water indicate that water near the bottom of the burial pit would migrate laterally in the shallow, weathered till for 5 to 6 meters before moving downward into the unweathered till, and water near the top of the pit would move laterally less than 20 meters before moving downward into the unweathered till. These results indicate that subsurface migration of radionuclides in groundwater to points of discharge to land surface is unlikely as long as the water level does not rise into the reworked cover material. (Author 's abstract)

  5. Geology of the Powder River Basin, Wyoming and Montana, with reference to subsurface disposal of radioactive wastes

    USGS Publications Warehouse

    Beikman, Helen M.

    1962-01-01

    The Powder River Basin is a structural and topographic basin occupying an area of about 20,000 square miles in northeastern Wyoming arid southeastern Montana. The Basin is about 230 miles long in a northwest-southeast direction and is about 100 miles wide. It is bounded on three sides by mountains in which rocks of Precambrian age are exposed. The Basin is asymmetrical with a steep west limb adjacent to the Bighorn Mountains and a gentle east limb adjacent to the Black Hills. Sedimentary rocks within the Basin have a maximum thickness of about 18,000 feet and rocks of every geologic period are represented. Paleozoic rocks are about 2,500 feet thick and consist of marine bonate rocks and sandstone; Mesozoic rocks are about 9,500 feet thick and consist of both marine and nonmarine siltstone and sandstone; and Cenozoic rocks are from 4,000 to 6,000 feet thick and consist of coal-bearing sandstone and shale. Radioactive waste could be stored in the pore space of permeable sandstone or in shale where space could be developed. Many such rock units that could be used for storing radioactive wastes are present within the Powder River Basin. Permeable sandstone beds that may be possible reservoirs for storage of radioactive waste are present throughout the Powder River Basin. These include sandstone beds in the Flathead Sandstone and equivalent strata in the Deadwood Formation, the Tensleep Sandstone and equivalent strata in the Minnelusa Formation and the Sundance Formation in rocks of pre-Cretaceous age. However, most of the possible sandstone reservoirs are in rocks of Cretaceous age and include sandstone beds in the Fall River, Lakota, Newcastle, Frontier, Cody, and Mesaverde Formations. Problems of containment of waste such as clogging of pore space and chemical incompatibility would have to be solved before a particular sandstone unit could be selected for waste disposal. Several thick sequences of impermeable shale such as those in the Skull Creek, Mowry, Frontier, Belle Fourche, Cody, Lewis, and Pierre Formations, occur in rocks of Cretaceous age in the Basin. Limited storage space for liquid waste might be developed in impermeable shale by fracturing the shale and space for calcined or fused waste could be developed by mining cavities.

  6. Mapping Fractures in KAERI Underground Research Tunnel using Ground Penetrating Radar

    NASA Astrophysics Data System (ADS)

    Baek, Seung-Ho; Kim, Seung-Sep; Kwon, Jang-Soon

    2016-04-01

    The proportion of nuclear power in the Republic of Korea occupies about 40 percent of the entire electricity production. Processing or disposing nuclear wastes, however, remains one of biggest social issues. Although low- and intermediate-level nuclear wastes are stored temporarily inside nuclear power plants, these temporary storages can last only up to 2020. Among various proposed methods for nuclear waste disposal, a long-term storage using geologic disposal facilities appears to be most highly feasible. Geological disposal of nuclear wastes requires a nuclear waste repository situated deep within a stable geologic environment. However, the presence of small-scale fractures in bedrocks can cause serious damage to durability of such disposal facilities because fractures can become efficient pathways for underground waters and radioactive wastes. Thus, it is important to find and characterize multi-scale fractures in bedrocks hosting geologic disposal facilities. In this study, we aim to map small-scale fractures inside the KAERI Underground Research Tunnel (KURT) using ground penetrating radar (GPR). The KURT is situated in the Korea Atomic Energy Research Institute (KAERI). The survey target is a section of wall cut by a diamond grinder, which preserves diverse geologic features such as dykes. We conducted grid surveys on the wall using 500 MHz and 1000 MHz pulseEKKO PRO sensors. The observed GPR signals in both frequencies show strong reflections, which are consistent to form sloping planes. We interpret such planar features as fractures present in the wall. Such fractures were also mapped visually during the development of the KURT. We confirmed their continuity into the wall from the 3D GPR images. In addition, the spatial distribution and connectivity of these fractures are identified from 3D subsurface images. Thus, we can utilize GPR to detect multi-scale fractures in bedrocks, during and after developing underground disposal facilities. This study was supported by Korea National Research Foundation (NRF) grants NRF-2012M2A8A5007440 and NRF-2013R1A1A1076071 funded by the Ministry of Science, ICT & Future Planning, Korea.

  7. Long-term surveillance plan for the Bodo Canyon Disposal Site, Durango, Colorado

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

    Not Available

    1994-03-01

    This long-term surveillance plan (LTSP) for the Durango, Colorado, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Durango (Bodo Canyon) disposal site, which will be referred to as the disposal site throughout this document. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal site continues to function as designed. This LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). RRMs include tailings and other uranium ore processing wastesmore » still at the site, which the DOE determines to be radioactive. This LTSP is based on the DOE`s Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992).« less

  8. Row erupts over US firm's plan to import nuclear waste

    NASA Astrophysics Data System (ADS)

    Gwynne, Peter

    2008-06-01

    A controversy is brewing in the US over a plan by a firm in Utah to import, process and dispose of 20 000 tonnes of low-level radioactive waste from decommissioned nuclear reactors built in Italy by American companies. EnergySolutions intends to recycle some of this waste at a site near Oak Ridge, Tennessee, so that it can be re-used as shielding blocks in nuclear plants. The firm then wants to dispose of the remaining radioactive material at a site in Clive, Utah, where over 90% of low-level radioactive waste generated in the US is currently buried.

  9. Multi-discipline Waste Acceptance Process at the Nevada National Security Site - 13573

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

    Carilli, Jhon T.; Krenzien, Susan K.

    2013-07-01

    The Nevada National Security Site low-level radioactive waste disposal facility acceptance process requires multiple disciplines to ensure the protection of workers, the public, and the environment. These disciplines, which include waste acceptance, nuclear criticality, safety, permitting, operations, and performance assessment, combine into the overall waste acceptance process to assess low-level radioactive waste streams for disposal at the Area 5 Radioactive Waste Management Site. Four waste streams recently highlighted the integration of these disciplines: the Oak Ridge Radioisotope Thermoelectric Generators and Consolidated Edison Uranium Solidification Project material, West Valley Melter, and classified waste. (authors)

  10. A review and overview of nuclear waste management

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

    Murray, R.L.

    1984-12-31

    An understanding of the status and issues in the management of radioactive wastes is based on technical information on radioactivity, radiation, biological hazard of radiation exposure, radiation standards, and methods of protection. The fission process gives rise to radioactive fission products and neutron bombardment gives activation products. Radioactive wastes are classified according to source: defense, commercial, industrial, and institutional; and according to physical features: uranium mill tailings, high-level, transuranic, and low-level. The nuclear fuel cycle, which contributes a large fraction of annual radioactive waste, starts with uranium ore, includes nuclear reactor use for electrical power generation, and ends with ultimatemore » disposal of residues. The relation of spent fuel storage and reprocessing is governed by technical, economic, and political considerations. Waste has been successfully solidified in glass and other forms and choices of the containers for the waste form are available. Methods of disposal of high-level waste that have been investigated are transmutation by neutron bombardment, shipment to Antartica, deep-hole insertion, subseabed placement, transfer by rocket to an orbit in space, and disposal in a mined cavity. The latter is the favored method. The choices of host geological media are salt, basalt, tuff, and granite.« less

  11. Radioactive liquid wastes discharged to ground in the 200 Areas during 1976

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

    Mirabella, J.E.

    An overall summary is presented giving the radioactive liquid wastes discharged to ground during 1976 and since startup (for both total and decayed depositions) within the Production and Waste Management Division control zone (200 Area plateau). Overall summaries are also presented for 200 East Area and for 200 West Area. The data contain an estimate of the radioactivity discharged to individual ponds, cribs and specific retention sites within the Production and Waste Management Division during 1976 and from startup through December 31, 1976; an estimate of the decayed activities from startup through 1976; the location and reference drawings of eachmore » disposal site; and the usage dates of each disposal site. The estimates for the radioactivity discharged and for decayed activities dicharged from startup through December 31, 1976 are based upon Item 4 of the Bibliography. The volume of liquid discharged to the ponds also includes major nonradioactive streams. The wastes discharged during 1976 to each active disposal site are detailed on a month-to-month basis, along with the monthly maximum concentration and average concentration data. An estimate of the radioactivity discharged to each active site along with the remaining decayed activities is given.« less

  12. Taiwan industrial cooperation program technology transfer for low-level radioactive waste final disposal - phase I.

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

    Knowlton, Robert G.; Cochran, John Russell; Arnold, Bill Walter

    2007-01-01

    Sandia National Laboratories and the Institute of Nuclear Energy Research, Taiwan have collaborated in a technology transfer program related to low-level radioactive waste (LLW) disposal in Taiwan. Phase I of this program included regulatory analysis of LLW final disposal, development of LLW disposal performance assessment capabilities, and preliminary performance assessments of two potential disposal sites. Performance objectives were based on regulations in Taiwan and comparisons to those in the United States. Probabilistic performance assessment models were constructed based on limited site data using software including GoldSim, BLT-MS, FEHM, and HELP. These software codes provided the probabilistic framework, container degradation, waste-formmore » leaching, groundwater flow, radionuclide transport, and cover infiltration simulation capabilities in the performance assessment. Preliminary performance assessment analyses were conducted for a near-surface disposal system and a mined cavern disposal system at two representative sites in Taiwan. Results of example calculations indicate peak simulated concentrations to a receptor within a few hundred years of LLW disposal, primarily from highly soluble, non-sorbing radionuclides.« less

  13. Geotechnical, geological, and selected radionuclide retention characteristics of the radioactive waste disposal site near the Farallon Islands

    USGS Publications Warehouse

    Booth, J.S.; Winters, W.J.; Poppe, L.J.; Neiheisel, J.; Dyer, R.S.

    1989-01-01

    A geotechnical and geological investigation of the Farallon Islands low-level radioactive waste (LLW) disposal area was conducted to qualitatively assess the host sediments' relative effectiveness as a barrier to radionuclide migration, to estimate the portion of the barrier that is in contact with the waste packages at the three primary disposal sites, and to provide a basic physical description of the sediments. Box cores recovered from within the general disposal area at depths of 500, 1000, and 1500 m were subcored to provide samples (~30 cm in length) for detailed descriptions, textural and mineralogical analyses, and a suite of geotechnical tests (index property, CRS consolidation, and CIU triaxial compression). -from Authors

  14. Solid wastes from nuclear power production.

    PubMed Central

    Soule, H F

    1978-01-01

    Radioactivity in nuclear power effluents is negligible compared to that in retained wastes to be disposed of as solids. Two basic waste categories are those for which shallow disposal is accepted and those for which more extreme isolation is desired. The latter includes "high level" wastes and others contaminated with radionuclides with the unusual combined properties of long radioactive half-life and high specific radiotoxicity. The favored method for extreme isolation is emplacement in a deep stable geologic formation. Necessary technologies for waste treatment and disposal are considered available. The present program to implement these technologies is discussed, including the waste management significance of current policy on spent nuclear fuel reprocessing. Recent difficulties with shallow disposal of waste are summarized. PMID:738244

  15. Mapping Fluid Injection and Associated Induced Seismicity Using InSAR Analysis

    NASA Astrophysics Data System (ADS)

    Thorpe, S. D.; Tiampo, K. F.

    2016-12-01

    In recent years there has been a rise in unconventional oil and gas production in western North America which has been coupled with an increase in the number of earthquakes recorded in these regions, commonly referred to as "induced seismicity" (Ellsworth, 2013). As fluid is pumped into the subsurface during hydraulic fracturing or fluid disposal, the state of stress within the subsurface changes, potentially reactivating pre-existing faults and/or causing subsidence or uplift of the surface. This anthropogenic surface deformation also provides significant hazard to communities and structures surrounding these hydraulic fracturing or fluid disposal sites (Barnhart et al., 2014; Shirzaei et al., 2016). This study aims to relate, both spatially and temporally, this surface deformation to hydraulic fracturing and fluid disposal operations in Alberta (AB) and British Columbia (BC) using Differential Interferometric Synthetic Aperture Radar (InSAR) analysis. Satellite-based geodetic methods such as InSAR provide frequent measurements of ground deformation at high spatial resolution. Based on locations of previously identified induced seismicity in areas throughout AB and BC, images were acquired for multiple locations from the Canadian RADARSAT-2 satellite, including Fort St. John and Fox Creek, AB (Atkinson et al., 2016). Using advanced processing techniques, these images then were stacked to generate coherent interferograms. We present results from this processing as a set of time series that are correlated with both hydraulic fracturing and fluid disposal sites at each location. These results reveal the temporal and spatial relationship between well injection activity and associated induced seismicity in western Canada. Future work will utilise these time series to model subsurface fluid flow, providing important information regarding the nature of the subsurface structure and associated aquifer due to fluid injection and withdrawal.

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

    Dehmel, J.C.; Loomis, D.; Mauro, J.

    Under contract to the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, the firms of S. Cohen & Associates, Inc. (SC&A) and Eastern Research Group (ERG) have compiled a report that describes the physical, chemical, and radiological properties of Class-A low-level radioactive waste. The report also presents information characterizing various methods and facilities used to treat and dispose non-radioactive waste. A database management program was developed for use in accessing, sorting, analyzing, and displaying the electronic data provided by EG&G. The program was used to present and aggregate data characterizing the radiological, physical, and chemical properties of the wastemore » from descriptions contained in shipping manifests. The data thus retrieved are summarized in tables, histograms, and cumulative distribution curves presenting radionuclide concentration distributions in Class-A waste as a function of waste streams, by category of waste generators, and regions of the United States. The report also provides information characterizing methods and facilities used to treat and dispose non-radioactive waste, including industrial, municipal, and hazardous waste regulated under Subparts C and D of the Resource Conservation and Recovery Act (RCRA). The information includes a list of disposal options, the geographical locations of the processing and disposal facilities, and a description of the characteristics of such processing and disposal facilities. Volume 1 contains the Executive Summary, Volume 2 presents the Class-A waste database, Volume 3 presents the information characterizing non-radioactive waste management practices and facilities, and Volumes 4 through 7 contain Appendices A through P with supporting information.« less

  17. 77 FR 20077 - Request for a License To Export Radioactive Waste

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-04-03

    ... NUCLEAR REGULATORY COMMISSION Request for a License To Export Radioactive Waste Pursuant to 10 CFR..., 2012, radioactive waste tons of or disposal by a February 16, 2012, XW019, in the form of ash radioactive waste licensed facility 11005986. and non-conforming as contaminated in Mexico. material. ash and...

  18. Scenario for the safety assessment of near surface radioactive waste disposal in Serpong, Indonesia

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

    Purnomo, A.S.

    2007-07-01

    Near surface disposal has been practiced for some decades, with a wide variation in sites, types and amounts of wastes, and facility designs employed. Experience has shown that the effective and safe isolation of waste depends on the performance of the overall disposal system, which is formed by three major components or barriers: the site, the disposal facility and the waste form. The objective of radioactive waste disposal is to isolate waste so that it does not result in undue radiation exposure to humans and the environment. In near surface disposal, the disposal facility is located on or below themore » ground surface, where the protective covering is generally a few meters thick. These facilities are intended to contain low and intermediate level waste without appreciable quantities of long-lived radionuclides. Safety is the most important aspect in the applications of nuclear technology and the implementation of nuclear activities in Indonesia. This aspect is reflected by a statement in the Act Number 10 Year 1997, that 'The Development and use of nuclear energy in Indonesia has to be carried out in such away to assure the safety and health of workers, the public and the protection of the environment'. Serpong are one of the sites for a nuclear research center facility, it is the biggest one in Indonesia. In the future will be developed the first near surface disposal on site of the nuclear research facility in Serpong. The paper will mainly focus on scenario of the safety assessments of near-surface radioactive waste disposal is often important to evaluate the performance of the disposal system (disposal facility, geosphere and biosphere). It will give detail, how at the present and future conditions, including anticipated and less probable events in order to prevent radionuclide migration to human and environment. Refer to the geology characteristic and ground water table is enable to place something Near Surface Disposal on unsaturated zone in Serpong site. (authors)« less

  19. Utilization of coal fly ash in solidification of liquid radioactive waste from research reactor.

    PubMed

    Osmanlioglu, Ahmet Erdal

    2014-05-01

    In this study, the potential utilization of fly ash was investigated as an additive in solidification process of radioactive waste sludge from research reactor. Coal formations include various percentages of natural radioactive elements; therefore, coal fly ash includes various levels of radioactivity. For this reason, fly ashes have to be evaluated for potential environmental implications in case of further usage in any construction material. But for use in solidification of radioactive sludge, the radiological effects of fly ash are in the range of radioactive waste management limits. The results show that fly ash has a strong fixing capacity for radioactive isotopes. Specimens with addition of 5-15% fly ash to concrete was observed to be sufficient to achieve the target compressive strength of 20 MPa required for near-surface disposal. An optimum mixture comprising 15% fly ash, 35% cement, and 50% radioactive waste sludge could provide the solidification required for long-term storage and disposal. The codisposal of radioactive fly ash with radioactive sludge by solidification decreases the usage of cement in solidification process. By this method, radioactive fly ash can become a valuable additive instead of industrial waste. This study supports the utilization of fly ash in industry and the solidification of radioactive waste in the nuclear industry.

  20. 10 CFR 61.10 - Content of application.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.10 Content of application. An application to receive from others, possess and dispose of wastes containing or contaminated with source, byproduct or special nuclear material by land disposal must consist...

  1. 10 CFR 61.10 - Content of application.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.10 Content of application. An application to receive from others, possess and dispose of wastes containing or contaminated with source, byproduct or special nuclear material by land disposal must consist...

  2. 10 CFR 61.10 - Content of application.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.10 Content of application. An application to receive from others, possess and dispose of wastes containing or contaminated with source, byproduct or special nuclear material by land disposal must consist...

  3. 10 CFR 61.10 - Content of application.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.10 Content of application. An application to receive from others, possess and dispose of wastes containing or contaminated with source, byproduct or special nuclear material by land disposal must consist...

  4. 10 CFR 61.10 - Content of application.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.10 Content of application. An application to receive from others, possess and dispose of wastes containing or contaminated with source, byproduct or special nuclear material by land disposal must consist...

  5. The Use of Induction Melting for the Treatment of Metal Radioactive Waste - 13088

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

    Zherebtsov, Alexander; Pastushkov, Vladimir; Poluektov, Pavel

    2013-07-01

    The aim of the work is to assess the efficacy of induction melting metal for recycling radioactive waste in order to reduce the volume of solid radioactive waste to be disposed of, and utilization of the metal. (authors)

  6. Low-Activity Radioactive Wastes

    EPA Pesticide Factsheets

    In 2003 EPA published an Advance Notice of Proposed Rulemaking (ANPR) to collect public comment on alternatives for disposal of waste containing low concentrations of radioactive material ('low-activity' waste).

  7. Development and application of a safety assessment methodology for waste disposals

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

    Little, R.H.; Torres, C.; Schaller, K.H.

    1996-12-31

    As part of a European Commission funded research programme, QuantiSci (formerly the Environmental Division of Intera Information Technologies) and Instituto de Medio Ambiente of the Centro de Investigaciones Energeticas Medioambientales y Tecnologicas (IMA/CIEMAT) have developed and applied a comprehensive, yet practicable, assessment methodology for post-disposal safety assessment of land-based disposal facilities. This Safety Assessment Comparison (SACO) Methodology employs a systematic approach to the collection, evaluation and use of waste and disposal system data. It can be used to assess engineered barrier performance, the attenuating properties of host geological formations, and the long term impacts of a facility on the environmentmore » and human health, as well as allowing the comparison of different disposal options for radioactive, mixed and non-radioactive wastes. This paper describes the development of the methodology and illustrates its use.« less

  8. 10 CFR 61.16 - Other information.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.16 Other information. Depending upon the nature of the wastes to be disposed of, and the design and proposed operation of the land disposal facility, additional information may be requested by the Commission...

  9. 10 CFR 61.16 - Other information.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.16 Other information. Depending upon the nature of the wastes to be disposed of, and the design and proposed operation of the land disposal facility, additional information may be requested by the Commission...

  10. 10 CFR 61.16 - Other information.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.16 Other information. Depending upon the nature of the wastes to be disposed of, and the design and proposed operation of the land disposal facility, additional information may be requested by the Commission...

  11. 10 CFR 61.16 - Other information.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.16 Other information. Depending upon the nature of the wastes to be disposed of, and the design and proposed operation of the land disposal facility, additional information may be requested by the Commission...

  12. 10 CFR 61.16 - Other information.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.16 Other information. Depending upon the nature of the wastes to be disposed of, and the design and proposed operation of the land disposal facility, additional information may be requested by the Commission...

  13. Study of extraterrestrial disposal of radioactive wastes. Part 2: Preliminary feasibility screening study of extraterrestrial disposal of radioactive wastes in concentrations, matrix materials, and containers designed for storage on earth

    NASA Technical Reports Server (NTRS)

    Hyland, R. E.; Wohl, M. L.; Thompson, R. L.; Finnegan, P. M.

    1972-01-01

    The results are reported of a preliminary feasibility screening study for providing long-term solutions to the problems of handling and managing radioactive wastes by extraterrestrial transportation of the wastes. Matrix materials and containers are discussed along with payloads, costs, and destinations for candidate space vehicles. The conclusions reached are: (1) Matrix material such as spray melt can be used without exceeding temperature limits of the matrix. (2) The cost in mills per kw hr electric, of space disposal of fission products is 4, 5, and 28 mills per kw hr for earth escape, solar orbit, and solar escape, respectively. (3) A major factor effecting cost is the earth storage time. Based on a normal operating condition design for solar escape, a storage time of more than sixty years is required to make the space disposal charge less than 10% of the bus-bar electric cost. (4) Based on a 10 year earth storage without further processing, the number of shuttle launches required would exceed one per day.

  14. Ground-water levels and precipitation data at the Maxey Flats low-level radioactive waste disposal site near Morehead, Kentucky, October 1988-September 2000

    USGS Publications Warehouse

    Zettwoch, Douglas D.

    2002-01-01

    The U.S. Geological Survey, in cooperation with the Kentucky Natural Resources and Environmental Protection Cabinet--Department for Environmental Protection--Division of Waste Management, has an ongoing program to monitor water levels at the Maxey Flats low-level radioactive waste disposal site near Morehead, Kentucky. Ground-water-level and precipitation data were collected from 112 wells and 1 rain gage at the Maxey Flats low-level radioactive waste disposal site during October 1988-September 2000. Data were collected on a semi-annual basis from 62 wells, continuously from 6 wells, and monthly or bimonthly from 44 wells (13 of which had continuous recorders installed for the period October 1998-September 2000). One tipping-bucket rain gage was used to collect data at the Maxey Flats site for the period October 1988-September 2000.

  15. 3rd Quarter Transportation Report FY 2014: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

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

    Gregory, Louis

    2014-09-20

    This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the 3rd quarter of Fiscal Year (FY) 2014 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. This report also includes annual summaries for FY 2014 in Tables 4 and 5. Tabular summaries are provided which includemore » the following: Sources of and carriers for LLW and MLLW shipments to and from the NNSS; Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report do not include minor volumes of non-radioactive materials that were approved for disposal. Volume reports showing cubic feet generated using the Low-Level Waste Information System may vary slightly due to differing rounding conventions.« less

  16. Ty Lepionka Uses Disposal System Model to Communicate With Public

    ERIC Educational Resources Information Center

    Vassey, Emuel E., III

    1976-01-01

    A sanitarian uses a model to demonstrate installation and operation of a subsurface disposal system. The model contains a septic tank, inlet and outlet T's, distribution box, and drain lines in various stages of construction. The model is used to inform mobile home owners about environmental health practices. (MR)

  17. LABORATORY INVESTIGATION OF RESIDUAL LIQUID ORGANICS FROM SPILLS, LEAKS, AND THE DISPOSAL OF HAZARDOUS WASTES IN GROUNDWATER

    EPA Science Inventory

    Organic liquids that are essentially immiscible with water migrate through the subsurface under the influence of capillary, viscous, and buoyancy forces. These liquids originate from the improper disposal of hazardous wastes, and the spills and leaks of petroleum hydrocarbons a...

  18. Evaluation of the impact of lime softening waste disposal in natural environments

    EPA Science Inventory

    Drinking water treatment residues (WTR), generated from the lime softening processes, are commonly reused or disposed of in a number of applications; these include use as a soil amendment or a subsurface fill. Recently questions were posed by the Florida regulatory community on w...

  19. Topic I: Induced changes in hydrology at low-level radioactive waste repository sites: A section in Safe disposal of radionuclides in low-level radioactive-waste repository sites; Low-level radioactive-waste disposal workshop, U.S. Geological Survey, July 11-16, 1987, Big Bear Lake, Calif., Proceedings (Circular 1036)

    USGS Publications Warehouse

    Prudic, David E.; Dennehy, Kevin F.; Bedinger, Marion S.; Stevens, Peter R.

    1990-01-01

    Engineering practices, including the excavation of trenches, placement of waste, nature of waste forms, backfilling procedures and materials, and trench-cover construction and materials at low-level radioactive-waste repository sites greatly affect the geohydrology of the sites. Engineering practices are dominant factors in eventual stability and isolation of the waste. The papers presented relating to Topic I were discussions of the hydrogeologic setting at existing low-level radioactive-waste repository sites and changes in the hydrology induced by site operations. Papers summarizing detailed studies presented at this workshop include those at sites near Sheffield, Ill.; Oak Ridge National Laboratory, Tenn.; West Valley, N.Y.; Maxey Flats, Ky.; Barnwell, S.C.; and Beatty, Nev. 

  20. Improving radioactive waste management: an overview of the Environmental Protection Agency's low-activity waste effort.

    PubMed

    Schultheisz, Daniel J; Czyscinski, Kenneth S; Klinger, Adam D

    2006-11-01

    Radioactive waste disposal in the United States is marked by a fragmented regulatory system, with requirements that often focus on the origin or statutory definition of the waste, rather than the hazard of the material in question. It may be possible to enhance public protection by moving toward a system that provides disposal options appropriate for the hazard presented by the waste in question. This paper summarizes aspects of an approach focusing on the potential use, with appropriate conditions, of Resource Conservation and Recovery Act Subtitle-C hazardous waste landfills for disposal of "low-activity" wastes and public comments on the suggested approach.

  1. A critical review of the risks to water resources from unconventional shale gas development and hydraulic fracturing in the United States.

    PubMed

    Vengosh, Avner; Jackson, Robert B; Warner, Nathaniel; Darrah, Thomas H; Kondash, Andrew

    2014-01-01

    The rapid rise of shale gas development through horizontal drilling and high volume hydraulic fracturing has expanded the extraction of hydrocarbon resources in the U.S. The rise of shale gas development has triggered an intense public debate regarding the potential environmental and human health effects from hydraulic fracturing. This paper provides a critical review of the potential risks that shale gas operations pose to water resources, with an emphasis on case studies mostly from the U.S. Four potential risks for water resources are identified: (1) the contamination of shallow aquifers with fugitive hydrocarbon gases (i.e., stray gas contamination), which can also potentially lead to the salinization of shallow groundwater through leaking natural gas wells and subsurface flow; (2) the contamination of surface water and shallow groundwater from spills, leaks, and/or the disposal of inadequately treated shale gas wastewater; (3) the accumulation of toxic and radioactive elements in soil or stream sediments near disposal or spill sites; and (4) the overextraction of water resources for high-volume hydraulic fracturing that could induce water shortages or conflicts with other water users, particularly in water-scarce areas. Analysis of published data (through January 2014) reveals evidence for stray gas contamination, surface water impacts in areas of intensive shale gas development, and the accumulation of radium isotopes in some disposal and spill sites. The direct contamination of shallow groundwater from hydraulic fracturing fluids and deep formation waters by hydraulic fracturing itself, however, remains controversial.

  2. Subsurface Contamination Control

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

    Y. Yuan

    There are two objectives of this report, ''Subsurface Contamination Control''. The first is to provide a technical basis for recommending limiting radioactive contamination levels (LRCL) on the external surfaces of waste packages (WP) for acceptance into the subsurface repository. The second is to provide an evaluation of the magnitude of potential releases from a defective WP and the detectability of the released contents. The technical basis for deriving LRCL has been established in ''Retrieval Equipment and Strategy for Wp on Pallet'' (CRWMS M and O 2000g, 6.3.1). This report updates the derivation by incorporating the latest design information of themore » subsurface repository for site recommendation. The derived LRCL on the external surface of WPs, therefore, supercede that described in CRWMS M and O 2000g. The derived LRCL represent the average concentrations of contamination on the external surfaces of each WP that must not be exceeded before the WP is to be transported to the subsurface facility for emplacement. The evaluation of potential releases is necessary to control the potential contamination of the subsurface repository and to detect prematurely failed WPs. The detection of failed WPs is required in order to provide reasonable assurance that the integrity of each WP is intact prior to MGR closure. An emplaced WP may become breached due to manufacturing defects or improper weld combined with failure to detect the defect, by corrosion, or by mechanical penetration due to accidents or rockfall conditions. The breached WP may release its gaseous and volatile radionuclide content to the subsurface environment and result in contaminating the subsurface facility. The scope of this analysis is limited to radioactive contaminants resulting from breached WPs during the preclosure period of the subsurface repository. This report: (1) documents a method for deriving LRCL on the external surfaces of WP for acceptance into the subsurface repository; (2) provides a table of derived LRCL for nuclides of radiological importance; (3) Provides an as low as is reasonably achievable (ALARA) evaluation of the derived LRCL by comparing potential onsite and offsite doses to documented ALARA requirements; (4) Provides a method for estimating potential releases from a defective WP; (5) Provides an evaluation of potential radioactive releases from a defective WP that may become airborne and result in contamination of the subsurface facility; and (6) Provides a preliminary analysis of the detectability of a potential WP leak to support the design of an airborne release monitoring system.« less

  3. Special Analysis for the Disposal of the Materials and Energy Corporation Sealed Sources at the Area 5 Radioactive Waste Management Site

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

    Shott, Gregory

    This special analysis (SA) evaluates whether the Materials and Energy Corporation (M&EC) Sealed Source waste stream (PERM000000036, Revision 0) is suitable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). Disposal of the M&EC Sealed Source waste meets all U.S. Department of Energy (DOE) Manual DOE M 435.1-1, “Radioactive Waste Management Manual,” Chapter IV, Section P performance objectives (DOE 1999). The M&EC Sealed Source waste stream is recommended for acceptance without conditions.

  4. Remediation of subsurface and groundwater contamination with uranium from fuel fabrication facilities at Hanau (Germany)

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

    Nitzsche, Olaf; Thierfeldt, Stefan; Hummel, Lothar

    2013-07-01

    This paper presents aspects of site decommissioning and clearance of a former fuel fabrication facility (development and production of fuel assemblies for research reactors and HTR) at Hanau (Germany). The main pathways for environmental contamination were deposition on soil surface and topsoil and pollution of deep soil and the aquifer by waste water channel leakage. Soil excavation could be done by classical excavator techniques. An effective removal of material from the saturated zone was possible by using advanced drilling techniques. A large amount of demolished building structure and excavated soil had to be classified. Therefore the use of conveyor detectormore » was necessary. Nearly 100000 Mg of material (excavated soil and demolished building material) were disposed of at an underground mine. A remaining volume of 700 m{sup 3} was classified as radioactive waste. Site clearance started in 2006. Groundwater remediation and monitoring is still ongoing, but has already provided excellent results by reducing the remaining Uranium considerably. (authors)« less

  5. Diffusion of Radionuclides in Concrete and Soil

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

    Mattigod, Shas V.; Wellman, Dawn M.; Bovaird, Chase C.

    2012-04-25

    One of the methods being considered for safely disposing of Category 3 low-level radioactive wastes is to encase the waste in concrete. Such concrete encasement would contain and isolate the waste packages from the hydrologic environment and would act as an intrusion barrier. Any failure of concrete encasement may result in water intrusion and consequent mobilization of radionuclides from the waste packages. The mobilized radionuclides may escape from the encased concrete by mass flow and/or diffusion and move into the surrounding subsurface environment. Therefore, it is necessary to assess the performance of the concrete encasement structure and the ability ofmore » the surrounding soil to retard radionuclide migration. The objective of our study was to measure the diffusivity of Re, Tc and I in concrete containment and the surrounding vadose zone soil. Effects of carbonation, presence of metallic iron, and fracturing of concrete and the varying moisture contents in soil on the diffusivities of Tc and I were evaluated.« less

  6. Analysis of local acceptance of a radioactive waste disposal facility.

    PubMed

    Chung, Ji Bum; Kim, Hong-Kew; Rho, Sam Kew

    2008-08-01

    Like many other countries in the world, Korea has struggled to site a facility for radioactive waste for almost 30 years because of the strong opposition from local residents. Finally, in 2005, Gyeongju was established as the first Korean site for a radioactive waste facility. The objectives of this research are to verify Gyeongju citizens' average level of risk perception of a radioactive waste disposal facility as compared to other risks, and to explore the best model for predicting respondents' acceptance level using variables related to cost-benefit, risk perception, and political process. For this purpose, a survey is conducted among Gyeongju residents, the results of which are as follows. First, the local residents' risk perception of an accident in a radioactive waste disposal facility is ranked seventh among a total of 13 risks, which implies that nuclear-related risk is not perceived very highly by Gyeongju residents; however, its characteristics are still somewhat negative. Second, the comparative regression analyses show that the cost-benefit and political process models are more suitable for explaining the respondents' level of acceptance than the risk perception model. This may be the result of the current economic depression in Gyeongju, residents' familiarity with the nuclear industry, or cultural characteristics of risk tolerance.

  7. Current situation and future plans in radioactive waste management in Mexico

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

    Lopez, H.; Jimenez, M.

    1992-01-01

    A brief introduction is offered in this document in order to explain the importance which is given in Mexico to the safe management of radioactive wastes. The Secretaria de Energia, Minas e Industria Paraestatal is the organization responsible for this issue. Also, a brief historical background is offered so as to understand the evolution of these activities since they were originated. This background allows us to describe the present situation, which consists in a substantial change in the volume of produced radioactive wastes; in other words, before the present situation only the, nuclear wastes from the application of radioisotopes weremore » generated whereas currently, with the starting of commercial operation of the first unit of Laguna Verde Nuclear Power Plant (LVNPP), large volumes of industrial radioactive wastes are being generated. A mention is given as well of the acquired experience during more than 20 years of waste management and of the technologies which have been applied or practiced in the use and disposal of such wastes. Finally, some general trends in relation to the future planning are indicated, which essentially consist in the siting and characterization of a site so as to, design and construct a permanent disposal facility in order to dispose the operational radioactive wastes from LVNPP.« less

  8. 2nd Quarter Transportation Report FY 2014

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

    Gregory, L.

    2014-07-01

    This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the second quarter of fiscal year (FY) 2014 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. This report also includes annual summaries for FY 2014 in Tables 4 and 5. Tabular summaries are provided which includemore » the following: Sources of and carriers for LLW and MLLW shipments to and from the NNSS; Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report do not include minor volumes of non-radioactive materials that were approved for disposal. Volume reports showing cubic feet (ft3) generated using the Low-Level Waste Information System may vary slightly due to differing rounding conventions.« less

  9. Radioactive Wastes. Revised.

    ERIC Educational Resources Information Center

    Fox, Charles H.

    This publication is one of a series of information booklets for the general public published by the United States Atomic Energy Commission. This booklet deals with the handling, processing and disposal of radioactive wastes. Among the topics discussed are: The Nature of Radioactive Wastes; Waste Management; and Research and Development. There are…

  10. The Public and Technological Decisions.

    ERIC Educational Resources Information Center

    Abrams, Nancy E.; Primack, Joel R.

    1980-01-01

    Discussed is the pragmatic basis for involving the public in radioactive waste decisions. A model approach to involving the public in preparation of a national radioactive waste disposal plan is outlined. (RE)

  11. Murt user`s guide: A hybrid Lagrangian-Eulerian finite element model of multiple-pore-region solute transport through subsurface media

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

    Gwo, J.P.; Jardine, P.M.; Yeh, G.T.

    Matrix diffusion, a diffusive mass transfer process,in the structured soils and geologic units at ORNL, is believe to be an important subsurface mass transfer mechanism; it may affect off-site movement of radioactive wastes and remediation of waste disposal sites by locally exchanging wastes between soil/rock matrix and macropores/fractures. Advective mass transfer also contributes to waste movement but is largely neglected by researchers. This report presents the first documented 2-D multiregion solute transport code (MURT) that incorporates not only diffusive but also advective mass transfer and can be applied to heterogeneous porous media under transient flow conditions. In this report, theoreticalmore » background is reviewed and the derivation of multiregion solute transport equations is presented. Similar to MURF (Gwo et al. 1994), a multiregion subsurface flow code, multiplepore domains as suggested by previous investigators (eg, Wilson and Luxmoore 1988) can be implemented in MURT. Transient or steady-state flow fields of the pore domains can be either calculated by MURF or by modelers. The mass transfer process is briefly discussed through a three-pore-region multiregion solute transport mechanism. Mass transfer equations that describe mass flux across pore region interfaces are also presented and parameters needed to calculate mass transfer coefficients detailed. Three applications of MURT (tracer injection problem, sensitivity analysis of advective and diffusive mass transfer, hillslope ponding infiltration and secondary source problem) were simulated and results discussed. Program structure of MURT and functions of MURT subroutiness are discussed so that users can adapt the code; guides for input data preparation are provided in appendices.« less

  12. 40 CFR 268.20 - Waste specific prohibitions-Dyes and/or pigments production wastes.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS Prohibitions on Land... contaminated with radioactive wastes mixed with this waste are prohibited from land disposal. (b) The... applicable subpart D levels, the waste is prohibited from land disposal, and all requirements of part 268 are...

  13. 40 CFR 268.20 - Waste specific prohibitions-Dyes and/or pigments production wastes.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS Prohibitions on Land... contaminated with radioactive wastes mixed with this waste are prohibited from land disposal. (b) The... applicable subpart D levels, the waste is prohibited from land disposal, and all requirements of part 268 are...

  14. 40 CFR 268.20 - Waste specific prohibitions-Dyes and/or pigments production wastes.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS Prohibitions on Land... contaminated with radioactive wastes mixed with this waste are prohibited from land disposal. (b) The... applicable subpart D levels, the waste is prohibited from land disposal, and all requirements of part 268 are...

  15. 40 CFR 268.20 - Waste specific prohibitions-Dyes and/or pigments production wastes.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS Prohibitions on Land... contaminated with radioactive wastes mixed with this waste are prohibited from land disposal. (b) The... applicable subpart D levels, the waste is prohibited from land disposal, and all requirements of part 268 are...

  16. 40 CFR 268.20 - Waste specific prohibitions-Dyes and/or pigments production wastes.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS Prohibitions on Land... contaminated with radioactive wastes mixed with this waste are prohibited from land disposal. (b) The... applicable subpart D levels, the waste is prohibited from land disposal, and all requirements of part 268 are...

  17. 77 FR 73054 - Application for a License To Export Radioactive Waste

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-07

    ... NUCLEAR REGULATORY COMMISSION Application for a License To Export Radioactive Waste Pursuant to 10 CFR 110.70(b) ``Public Notice of Receipt of an Application,'' please take notice that the Nuclear..., October 25, 2012, XW020, radioactive 1178 pounds disposal by the 11006061. waste in the (approximately...

  18. 10 CFR 961.3 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... ENERGY STANDARD CONTRACT FOR DISPOSAL OF SPENT NUCLEAR FUEL AND/OR HIGH-LEVEL RADIOACTIVE WASTE General... means any person who has title to spent nuclear fuel or high-level radioactive waste. Purchaser means... (42 U.S.C. 2133, 2134) or who has title to spent nuclear fuel or high level radioactive waste and who...

  19. 75 FR 27842 - Request for a License to Export Radioactive Waste

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-05-18

    ... NUCLEAR REGULATORY COMMISSION Request for a License to Export Radioactive Waste Pursuant to 10 CFR... Duratek Services, Inc. (a Class A Approximately 680 Storage or Canada. subsidiary of radioactive pounds (53 cubic disposal by the EnergySolutions), April 19, waste in the feet) of dry original 2010, April...

  20. Transporting Radioactive Waste: An Engineering Activity. Grades 5-12.

    ERIC Educational Resources Information Center

    HAZWRAP, The Hazardous Waste Remedial Actions Program.

    This brochure contains an engineering activity for upper elementary, middle school, and high school students that examines the transportation of radioactive waste. The activity is designed to inform students about the existence of radioactive waste and its transportation to disposal sites. Students experiment with methods to contain the waste and…

  1. Using Geographic Information Systems to Determine Site Suitability for a Low-Level Radioactive Waste Storage Facility.

    PubMed

    Wilson, Charles A; Matthews, Kennith; Pulsipher, Allan; Wang, Wei-Hsung

    2016-02-01

    Radioactive waste is an inevitable product of using radioactive material in education and research activities, medical applications, energy generation, and weapons production. Low-level radioactive waste (LLW) makes up a majority of the radioactive waste produced in the United States. In 2010, over two million cubic feet of LLW were shipped to disposal sites. Despite efforts from several states and compacts as well as from private industry, the options for proper disposal of LLW remain limited. New methods for quickly identifying potential storage locations could alleviate current challenges and eventually provide additional sites and allow for adequate regional disposal of LLW. Furthermore, these methods need to be designed so that they are easily communicated to the public. A Geographic Information Systems (GIS) based method was developed to determine suitability of potential LLW disposal (or storage) sites. Criteria and other parameters of suitability were based on the Code of Federal Regulation (CFR) requirements as well as supporting literature and reports. The resultant method was used to assess areas suitable for further evaluation as prospective disposal sites in Louisiana. Criteria were derived from the 10 minimum requirements in 10 CFR Part 61.50, the Nuclear Regulatory Commission's Regulatory Guide 0902, and studies at existing disposal sites. A suitability formula was developed permitting the use of weighting factors and normalization of all criteria. Data were compiled into GIS data sets and analyzed on a cell grid of approximately 14,000 cells (covering 181,300 square kilometers) using the suitability formula. Requirements were analyzed for each cell using multiple criteria/sub-criteria as well as surrogates for unavailable datasets. Additional criteria were also added when appropriate. The method designed in this project proved to be sufficient for initial screening tests in determining the most suitable areas for prospective disposal (or storage) sites. Cells above 90%, 95%, and 99% suitability include respectively 404, 88, and 4 cells suitable for further analysis. With these areas identified, the next step in siting a LLW storage facility would be on-site analysis using additional requirements as specified by relevant regulatory guidelines. The GIS based method provides an easy, economic, efficient and effective means in evaluating potential sites for LLW storage facilities where sufficient GIS data exist.

  2. Experiences in the field of radioactive materials seizures in the Czech Republic

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

    Svoboda, Karel; Podlaha, Josef; Sir, David

    2007-07-01

    In recent years, the amount of radioactive materials seizures (captured radioactive materials) has been rising. It was above all due to newly installed detection facilities that were able to check metallic scrap during its collection in scrap yards or on the entrance to iron-mills, checking municipal waste upon entrance to municipal disposal sites, even incineration plants, or through checking vehicles going through the borders of the Czech Republic. Most cases bore a relationship to secondary raw materials or they were connected to the application of machines and installations made from contaminated metallic materials. However, in accordance to our experience, themore » number of cases of seizures of materials and devices containing radioactive sources used in the public domain was lower, but not negligible, in the municipal storage yards or incineration plants. Atomic Act No. 18/1997 Coll. will apply to everybody who provides activities leading to exposure, mandatory assurance as high radiation safety as risk of the endangering of life, personal health and environment is as low as reasonably achievable in according to social and economic aspects. Hence, attention on the examination of all cases of the radioactive material seizure based on detection facilities alarm or reasonably grounds suspicion arising from the other information is important. Therefore, a service carried out by group of workers who ensure assessment of captured radioactive materials and eventual retrieval of radioactive sources from the municipal waste has come into existence in the Nuclear Research Institute Rez plc. This service has covered also transport, storage, processing and disposal of found radioactive sources. This service has arisen especially for municipal disposal sites, but later on even other companies took advantage of this service like incineration plants, the State Office for Nuclear Safety, etc. Our experience in the field of ensuring assessment of captured radioactive materials and eventual retrieval of radioactive sources will be presented in the paper. (authors)« less

  3. The NEA research and environmental surveillance programme related to sea disposal of low-level radioactive waste

    NASA Astrophysics Data System (ADS)

    Rugger, B.; Templeton, W. L.; Gurbutt, P.

    1983-05-01

    Sea dumping operations of certain types of packaged low and medium level radioactive wastes have been carried out since 1967 in the North-East Atlantic under the auspices of the OECD Nuclear Energy Agency. On the occasion of the 1980 review of the continued suitability of the North-East Atlantic site used for the disposal of radioactive waste, it was recommended that an effort should be made to increase the scientific data base relating to the oceanographic and biological characteristics of the dumping area. In particular, it was suggested that a site specific model of the transfer of radionuclides in the marine environment be developed, which would permit a better assessment of the potential radiation doses to man from the dumping of radioactive waste. To fulfill these objectives a research and environmental surveillance program related to sea disposal of radioactive waste was set up in 1981 with the participation of thirteen Member countries and the International Laboratory for Marine Radioactivity of the IAEA in Monaco. The research program is focused on five research areas which are directly relevant to the preparation of more site specific assessments in the future. They are: model development; physical oceanography; geochemistry; biology; and radiological surveillance. Promising results have already been obtained and more are anticipated in the not too distant future. An interim description of the NEA dumping site has been prepared which provides an excellent data base for this area.

  4. Process for disposal of aqueous solutions containing radioactive isotopes

    DOEpatents

    Colombo, Peter; Neilson, Jr., Robert M.; Becker, Walter W.

    1979-01-01

    A process for disposing of radioactive aqueous waste solutions whereby the waste solution is utilized as the water of hydration to hydrate densified powdered portland cement in a leakproof container; said waste solution being dispersed without mechanical inter-mixing in situ in said bulk cement, thereafter the hydrated cement body is impregnated with a mixture of a monomer and polymerization catalyst to form polymer throughout the cement body. The entire process being carried out while maintaining the temperature of the components during the process at a temperature below 99.degree. C. The container containing the solid polymer-impregnated body is thereafter stored at a radioactive waste storage dump such as an underground storage dump.

  5. S. 1111: This Act may be cited as the Radiation Protection Act of 1991, introduced in the US Senate, One Hundred Second Congress, First Session, May 21, 1991

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

    Not Available

    1991-01-01

    This bill was introduced into the US Senate on May 21, 1991 to protect the public from health risks from radiation exposure from low-level radioactive waste. Key features of this legislation which are discussed include the following: state authority for fees or charges for waste storage and disposal facilities; and state authority to regulate disposal of low-level radioactive waste.

  6. Water-vapor movement through unsaturated alluvium in Amargosa Desert near Beatty, Nevada - Current understanding and continuing studies: A section in Joint US Geological Survey, US Nuclear Regulatory Commission workshop on research related to low-level radioactive waste disposal, May 4-6, 1993, National Center, Reston, Virginia; Proceedings (WRI 95-4015)

    USGS Publications Warehouse

    Prudic, David E.; Stevens, Peter R.; Nicholson, Thomas J.

    1996-01-01

    Disposal of low-level radioactive wastes has been a concern since the 1950's. These wastes commonly are buried in shallow trenches (Fischer, 1986, p. 2). Water infiltrating into the trenches is considered the principal process by which contaminants are transported away from the buried wastes, although gaseous transport in some areas may be important. Arid regions in the western United States have been suggested as places that could provide safe containment of the wastes, because little or no water would infiltrate into the trenches (Richardson, 1962), and because thick unsaturated zones would slow contaminant movement. Although burial in arid regions may greatly reduce the amount of water coming in contact with the waste and consequently may provide longterm containment, insufficient data are available on the effectiveness of burial in such regions. Of particular interest is the potential for contaminant movement, either as liquid or vapor, through unsaturated sediments to land surface or to underlying ground water.Since 1962, low-level radioactive wastes have been buried at a disposal facility in the Amargosa Desert, about 17 km south of Beatty, Nevada (fig. 50). This facility is in one of the most arid regions of the United States. Annual precipitation at the disposal facility averaged 82 mm for 1985-92; the minimum was 14 mm, recorded for 1989 (Wood and Andraski, 1992, p. 12).Investigations to determine the hydrogeology, water movement, and potential for contaminant movement at the facility began in 1976. Results from an initial study indicated that a potential exists for deep percolation of infiltrated water at the burial site (Nichols, 1987), assuming that the only water loss is by evaporation because the trenches are kept clear of vegetation. Results from a subsequent study of water movement beneath an undisturbed, vegetated site indicate that percolation of infiltrated water may be limited to the uppermost 9 m of sediments, on the basis of water potentials, subsurface temperatures, water content, and sodium chloride content of the sediments (Fischer, 1992, p. 1). One objective of a third study that began in 1987 is to determine how the typical procedure of burying wastes alters water movement and affects the potential for deep percolation of infiltrated water (Andraski, these proceedings). In addition to these studies, a fourth began in 1992 to determine the importance of vapor movement through the unsaturated zone.The purpose of this paper is to summarize the current understanding of water movement (as liquid and vapor) through the upper 13 m of unsaturated sediments beneath the undisturbed, vegetated site and to present plans for determining the importance of watervapor movement from land surface to the water table.

  7. Canister Design for Deep Borehole Disposal of Nuclear Waste

    DTIC Science & Technology

    2006-05-01

    radioactive waste disposal (not yet released) Fortunately, transportation casks for spent fuel have already been approved, built, and used as...would allow use of the current designs for transportation casks ; or, place the fuel assemblies into the final disposal canisters 21 prior to transport ...16 Figure 1-5. Typical Spent Fuel Transportation Casks

  8. 10 CFR 61.54 - Alternative requirements for design and operations.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... Section 61.54 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.54 Alternative requirements for... other than those set forth in §§ 61.51 through 61.53 for the segregation and disposal of waste and for...

  9. 10 CFR 61.54 - Alternative requirements for design and operations.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... Section 61.54 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.54 Alternative requirements for... other than those set forth in §§ 61.51 through 61.53 for the segregation and disposal of waste and for...

  10. 10 CFR 61.54 - Alternative requirements for design and operations.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... Section 61.54 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.54 Alternative requirements for... other than those set forth in §§ 61.51 through 61.53 for the segregation and disposal of waste and for...

  11. 10 CFR 61.54 - Alternative requirements for design and operations.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... Section 61.54 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.54 Alternative requirements for... other than those set forth in §§ 61.51 through 61.53 for the segregation and disposal of waste and for...

  12. 10 CFR 61.54 - Alternative requirements for design and operations.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... Section 61.54 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.54 Alternative requirements for... other than those set forth in §§ 61.51 through 61.53 for the segregation and disposal of waste and for...

  13. Improving Site-Specific Radiological Performance Assessments - 13431

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

    Tauxe, John; Black, Paul; Catlett, Kate

    2013-07-01

    An improved approach is presented for conducting complete and defensible radiological site-specific performance assessments (PAs) to support radioactive waste disposal decisions. The basic tenets of PA were initiated some thirty years ago, focusing on geologic disposals and evaluating compliance with regulations. Some of these regulations were inherently probabilistic (i.e., addressing uncertainty in a quantitative fashion), such as the containment requirements of the U.S. Environmental Protection Agency's (EPA's) 40 CFR 191, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, Chap. 191.13 [1]. Methods of analysis were developed to meet those requirements, butmore » at their core early PAs used 'conservative' parameter values and modeling approaches. This limited the utility of such PAs to compliance evaluation, and did little to inform decisions about optimizing disposal, closure and long-term monitoring and maintenance, or, in general, maintaining doses 'as low as reasonably achievable' (ALARA). This basic approach to PA development in the United States was employed essentially unchanged through the end of the 20. century, principally by the U.S. Department of Energy (DOE). Performance assessments developed in support of private radioactive waste disposal operations, regulated by the U.S. Nuclear Regulatory Commission (NRC) and its agreement states, were typically not as sophisticated. Discussion of new approaches to PA is timely, since at the time of this writing, the DOE is in the midst of revising its Order 435.1, Radioactive Waste Management [2], and the NRC is revising 10 CFR 61, Licensing Requirements for Land Disposal of Radioactive Waste [3]. Over the previous decade, theoretical developments and improved computational technology have provided the foundation for integrating decision analysis (DA) concepts and objective-focused thinking, plus a Bayesian approach to probabilistic modeling and risk analysis, to guide improvements in PA. This decision-making approach, [4, 5, 6] provides a transparent formal framework for using a value- or objective-focused approach to decision-making. DA, as an analytical means to implement structured decision making, provides a context for both understanding how uncertainty affects decisions and for targeting uncertainty reduction. The proposed DA approach improves defensibility and transparency of decision-making. The DA approach is fully consistent with the need to perform realistic modeling (rather than conservative modeling), including evaluation of site-specific factors. Instead of using generic stylized scenarios for radionuclide fate and transport and for human exposures to radionuclides, site-specific scenarios better represent the advantages and disadvantages of alternative disposal sites or engineered designs, thus clarifying their differences as well as providing a sound basis for evaluation of site performance. The full DA approach to PA is described, from explicitly incorporating societal values through stakeholder involvement to model building. Model building involves scoping by considering features, events, processes, and exposure scenarios (FEPSs), development of a conceptual site model (CSM), translation into numerical models and subsequent computation, and model evaluation. These are implemented in a cycle of uncertainty analysis, sensitivity analysis and value of information analysis so that uncertainty can be reduced until sufficient confidence is gained in the decisions to be made. This includes the traditional focus on hydrogeological processes, but also places emphasis on other FEPSs such as biotically-induced transport and human exposure phenomena. The significance of human exposure scenarios is emphasized by modifying the traditional acronym 'FEPs' to include them, hence 'FEPSs'. The radioactive waste community is also recognizing that disposal sites are to be considered a national (or even global) resource. As such, there is a pressing need to optimize their utility within the constraints of protecting human health and the environment. Failing to do so will result in the need for additional sites or options for storing radioactive waste temporarily, assuming a continued need for radioactive waste disposal. Optimization should be performed using DA, including economic analysis, invoked if necessary through the ALARA process. The economic analysis must recognize the cost of implementation (disposal design, closure, maintenance, etc.), and intra- and inter-generational equity in order to ensure that the best possible radioactive waste management decisions are made for the protection of both current and future generations. In most cases this requires consideration of population or collective risk. (authors)« less

  14. Impact of microbial activity on the radioactive waste disposal: long term prediction of biocorrosion processes.

    PubMed

    Libert, Marie; Schütz, Marta Kerber; Esnault, Loïc; Féron, Damien; Bildstein, Olivier

    2014-06-01

    This study emphasizes different experimental approaches and provides perspectives to apprehend biocorrosion phenomena in the specific disposal environment by investigating microbial activity with regard to the modification of corrosion rate, which in turn can have an impact on the safety of radioactive waste geological disposal. It is found that iron-reducing bacteria are able to use corrosion products such as iron oxides and "dihydrogen" as new energy sources, especially in the disposal environment which contains low amounts of organic matter. Moreover, in the case of sulphate-reducing bacteria, the results show that mixed aerobic and anaerobic conditions are the most hazardous for stainless steel materials, a situation which is likely to occur in the early stage of a geological disposal. Finally, an integrated methodological approach is applied to validate the understanding of the complex processes and to design experiments aiming at the acquisition of kinetic data used in long term predictive modelling of biocorrosion processes. © 2013.

  15. 10 CFR 62.12 - Contents of a request for emergency access: General information.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... EMERGENCY ACCESS TO NON-FEDERAL AND REGIONAL LOW-LEVEL WASTE DISPOSAL FACILITIES Request for a Commission... the person(s) or company(ies) generating the low-level radioactive waste for which the determination...) Certification that the radioactive waste for which emergency access is requested is low-level radioactive waste...

  16. 10 CFR 61.41 - Protection of the general population from releases of radioactivity.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Protection of the general population from releases of radioactivity. 61.41 Section 61.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.41 Protection of the general population...

  17. 10 CFR 61.41 - Protection of the general population from releases of radioactivity.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Protection of the general population from releases of radioactivity. 61.41 Section 61.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.41 Protection of the general population...

  18. 10 CFR 61.41 - Protection of the general population from releases of radioactivity.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Protection of the general population from releases of radioactivity. 61.41 Section 61.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.41 Protection of the general population...

  19. 10 CFR 61.41 - Protection of the general population from releases of radioactivity.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Protection of the general population from releases of radioactivity. 61.41 Section 61.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.41 Protection of the general population...

  20. 10 CFR 61.41 - Protection of the general population from releases of radioactivity.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Protection of the general population from releases of radioactivity. 61.41 Section 61.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.41 Protection of the general population...

  1. Development of Approach for Long-Term Management of Disused Sealed Radioactive Sources - 13630

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

    Kinker, M.; Reber, E.; Mansoux, H.

    Radioactive sources are used widely throughout the world in a variety of medical, industrial, research and military applications. When such radioactive sources are no longer used and are not intended to be used for the practice for which an authorization was granted, they are designated as 'disused sources'. Whether appropriate controls are in place during the useful life of a source or not, the end of this useful life is often a turning point after which it is more difficult to ensure the safety and security of the source over time. For various reasons, many disused sources cannot be returnedmore » to the manufacturer or the supplier for reuse or recycling. When these attempts fail, disused sources should be declared as radioactive waste and should be managed as such, in compliance with relevant international legal instruments and safety standards. However, disposal remains an unresolved issue in many counties, due to in part to limited public acceptance, insufficient funding, and a lack of practical examples of strategies for determining suitable disposal options. As a result, disused sources are often stored indefinitely at the facilities where they were once used. In order to prevent disused sources from becoming orphan sources, each country must develop and implement a comprehensive waste management strategy that includes disposal of disused sources. The International Atomic Energy Agency (IAEA) fosters international cooperation between countries and encourages the development of a harmonized 'cradle to grave' approach to managing sources consistent with international legal instruments, IAEA safety standards, and international good practices. This 'cradle to grave' approach requires the development of a national policy and implementing strategy, an adequate legal and regulatory framework, and adequate resources and infrastructure that cover the entire life cycle, from production and use of radioactive sources to disposal. (authors)« less

  2. Putting Radioactive Wastes on Ice: A Proposal for an International Radionuclide Depository in Antarctica

    ERIC Educational Resources Information Center

    Zeller, E. J.; And Others

    1973-01-01

    Describes need for creating permanent disposal of high-level radioactive wastes accumulating in different countries. Possibilities of establishing facilities for this purpose in Antarctic ice cap are examined. (PS)

  3. NRC`s proposed rulemaking on the documentation and reporting of low-level radioactive waste shipment manifest information

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

    Lahs, W.R.; Haisfield, M.F.

    1991-12-31

    Since the 1982 promulgation of regulations for the land disposal of low-level radioactive waste (LLW), requirements have been in place to control transfers of LLW intended for disposal at licensed land disposal facilities. These requirements established a manifest tracking system and defined processes to control transfers of LLW intended for disposal at a land disposal facility. Because the regulations did not specify the format for the LLW shipment manifests, it was not unexpected that the two operators of the three currently operating disposal sites should each have developed their own manifest forms. The forms have many similarities and the collectedmore » information, in many cases, is identical; however, these manifests incorporate unique operator preferences and also reflect the needs of the Agreement State regulatory authority in the States where the disposal sites are located. Since Agreement State regulations must be compatible with, but need not always be identical to, those of the Nuclear Regulatory Commission (NRC), the possibility of a proliferation of different manifest forms containing variations in collected information could be envisioned. If these manifests were also to serve a shipping paper purpose, effective integration of the Department of Transportations` (DOT) requirements would also have to be addressed. This wide diversity in uses of manifest information by Federal and State regulatory authorities, other State or Compact entities, and disposal site operators, suggested a single consolidated approach to develop a uniform manifest format with a baseline information content and to define recordkeeping requirements. The NRC, in 1989, had embarked on a rulemaking activity to establish a base set of manifest information needs for regulatory purposes. In response to requests from State and Regional Compact organizations who are attempting to design, develop and operate LLW disposal facilities, and with the general support of Agreement State regulatory authorities, this original data base rulemaking was expanded to include development of a uniform low-level radioactive waste manifest.« less

  4. Carbon Tetrachloride Flow and Transport in the Subsurface of the 216-Z-9 Trench at the Hanford Site

    NASA Astrophysics Data System (ADS)

    Oostrom, M.; Rockhold, M.; Truex, M.; Thorne, P.; Last, G.; Rohay, V.

    2006-12-01

    Three-dimensional modeling was conducted with layered and heterogeneous models to enhance the conceptual model of CT distribution in the vertical and lateral direction beneath the 216-Z-9 trench and to investigate the effects of soil vapor extraction (SVE). This work supports the U.S. Department of Energy's (DOE's) efforts to characterize the nature and distribution of CT in the 200 West Area and subsequently select an appropriate final remedy. Simulations targeted migration of dense, nonaqueous phase liquid (DNAPL) consisting of CT and co-disposed organics in the subsurface beneath the 216-Z-9 trench as a function of the properties and distribution of subsurface sediments and of the properties and disposal history of the waste. Simulations of CT migration were conducted using the Subsurface Transport Over Multiple Phases (STOMP) simulator. Simulation results support a conceptual model for CT distribution where CT in the DNAPL phase is expected to have migrated primarily in a vertical direction below the disposal trench. Presence of small-scale heterogeneities tends to limit the extent of vertical migration of CT DNAPL due to enhanced retention of DNAPL compared to more homogeneous conditions, but migration is still predominantly in the vertical direction. Results also show that the Cold Creek units retain more CT DNAPL within the vadose zone than other hydrologic unit during SVE. A considerable amount of the disposed CT DNAPL may have partitioned to the vapor and subsequently water and sorbed phases. Presence of small-scale heterogeneities tends to increase the amount of volatilization. Any continued migration of CT from the vadose zone to the groundwater is likely through interaction of vapor phase CT with the groundwater and not through continued DNAPL migration. The results indicated that SVE appears to be an effective technology for vadose zone remediation, but additional effort is needed to improve simulation of the SVE process.

  5. Assessment for the management of NORM wastes in conventional hazardous and nonhazardous waste landfills.

    PubMed

    Mora, Juan C; Baeza, Antonio; Robles, Beatriz; Sanz, Javier

    2016-06-05

    Naturally Occurring Radioactive Materials (NORM) wastes are generated in huge quantities in several industries and their management has been carried out under considerations of industrial non-radioactive wastes, before the concern on the radioactivity content was included in the legislation. Therefore these wastes were conditioned using conventional methods and the waste disposals were designed to isolate toxic elements from the environment for long periods of time. Spanish regulation for these conventional toxic waste disposals includes conditions that assure adequate isolation to minimize the impact of the wastes to the environment in present and future conditions. After 1996 the radiological impact of the management of NORM wastes is considered and all the aspects related with natural radiations and the radiological control regarding the management of residues from NORM industries were developed in the new regulation. One option to be assessed is the disposal of NORM wastes in hazardous and non-hazardous waste disposals, as was done before this new regulation. This work analyses the management of NORM wastes in these landfills to derive the masses that can be disposed without considerable radiological impact. Generic dose assessments were carried out under highly conservative hypothesis and a discussion on the uncertainty and variability sources was included to provide consistency to the calculations. Copyright © 2016 Elsevier B.V. All rights reserved.

  6. Characterization and remediation of a mixed waste-contaminated site at Kirtland Air Force Base, New Mexico

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

    Johnston, J.W.; Thacker, M.S.; DeWitt, C.B.

    In the area of environmental restoration, one of the most challenging problems is the task of remediating mixed waste-contaminated sites. This paper discusses a successful Interim Corrective Measure (ICM) performed at a mixed waste-contaminated site on Kirtland Air Force Base (AFB) in Albuquerque, New Mexico. The site, known as RW-68, Cratering Area and Radium Dump/Slag Piles, was used during the late 1940s and early 1950s for the destruction and incineration of captured World War II aircraft. It contained 19 slag piles totaling approximately 150 tons of slag, ash, refractory brick, and metal debris. The piles were contaminated with radium-226 andmore » RCRA-characteristic levels of heavy metals. Therefore, the piles were considered mixed waste. To eliminate the threat to human health and the environment, an ICM of removal, segregation, stabilization, and disposal was conducted from October through December 1996. Approximately 120 cubic yards (cu yds) of mixed waste, 188 cu yds of low-level radioactive-contaminated soil, 1 cu yd of low-level radioactive-contaminated debris, 5 cu yds of RCRA-characteristic hazardous waste, and 45 tons of nonhazardous debris were stabilized and disposed of during the ICM. To render the RCRA metals and radionuclides insoluble, stabilization was performed on the mixed and RCRA-characteristic waste streams. All stabilized material was subjected to TCLP analysis to verify it no longer exhibited RCRA-characteristic properties. Radiological and geophysical surveys were conducted concurrently with site remediation activities. These surveys provided real-time documentation of site conditions during each phase of the ICM and confirmed successful cleanup of the site. The three radioactive waste streams, stabilized mixed waste, low-level radioactive-contaminated soil, and low-level radioactive-contaminated debris, were disposed of at the Envirocare low-level radioactive disposal facility.« less

  7. [Investigation of radioactivity measurement of medical radioactive waste].

    PubMed

    Koizumi, Kiyoshi; Masuda, Kazutaka; Kusakabe, Kiyoko; Kinoshita, Fujimi; Kobayashi, Kazumi; Yamamoto, Tetsuo; Kanaya, Shinichi; Kida, Tetsuo; Yanagisawa, Masamichi; Iwanaga, Tetsuo; Ikebuchi, Hideharu; Kusama, Keiji; Namiki, Nobuo; Okuma, Hiroshi; Fujimura, Yoko; Horikoshi, Akiko; Tanaka, Mamoru

    2004-11-01

    To explore the possibility of which medical radioactive wastes could be disposed as general wastes after keeping them a certain period of time and confirming that their radioactivity reach a background level (BGL), we made a survey of these wastes in several nuclear medicine facilities. The radioactive wastes were collected for one week, packed in a box according to its half-life, and measured its radioactivity by scintillation survey meter with time. Some wastes could reach a BGL within 10 times of half-life, but 19% of the short half-life group (group 1) including 99mTc and 123I, and 8% of the middle half-life group (group 2) including 67Ga, (111)In, and 201Tl did not reach a BGL within 20 times of half-life. A reason for delaying the time of reaching a BGL might be partially attributed to high initial radiation dose rate or heavy package weight. However, mixing with the nuclides of longer half-life was estimated to be the biggest factor affecting this result. When disposing medical radioactive wastes as general wastes, it is necessary to avoid mixing with radionuclide of longer half-life and confirm that it reaches a BGL by actual measurement.

  8. Hydrologic conditions at the Idaho National Engineering Laboratory, Idaho, emphasis; 1974-1978

    USGS Publications Warehouse

    Barraclough, Jack T.; Lewis, Barney D.; Jensen, Rodger G.

    1981-01-01

    Aqueous chemical and radioactive wastes have been discharged to shallow ponds and to shallow or deep wells on the Idaho National Engineering Laboratory (INEL) since 1952 and has affected the quality of the ground water in the underlying Snake River Plain aquifer. Ongoing studies conducted from 1974 through 1978 have shown the perpetuation of a perched ground-water zone in the basalt underlying the waste disposal ponds at the INEL 's Test Reactor Area and of several waste plumes in the regional aquifer created by deep well disposal at the Idaho Chemical Processing Plant (ICPP). The perched zone contains tritium, chromium-51, cobalt-60, strontium-90, and several nonradioactive chemicals. Tritium has formed the largest waste plume south of the ICPP, and accounts for 95 percent of the total radioacticity disposed of through the ICPP disposal well. Waste plumes with similar configurations and flowpaths contain sodium, chloride, and nitrate. Strontium-90, iodine-129, and cesium-137 are also discharged through the well but they are sorbed from solution as they move through the aquifer or are discharged in very small quantities. Strontium-90 and iodine-129 have formed small waste plumes and cesium-137 is not detectable in ground-water samples. Radionuclide plume size and concentrations therein are controlled by aquifer flow conditions, the quantity discharged, radioactive decay, sorption, dilution by dispersion, and perhaps other chemical reactions. Chemical wastes are subject to the same processes except for radioactive decay. (USGS)

  9. Radioactive waste management in France and international cooperation

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

    Marque, Y.

    1991-01-01

    Long-term industrial management of radioactive waste in France is carried out by the Agence Nationale pour la gestion des Dechets Radioactifs. (ANDRA), which is a public body responsible mainly for siting, design, construction, and operation of the disposal facilities for every kind of radioactive waste produced in the country. Furthermore, ANDRA has to define and control the required quality of waste packages delivered for disposal. As far as disposal is concerned, it is customary in France to classify waste in two main categories. The first category includes all the so-called short-lived low-level waste (LLW) containing mainly radioactive substances have

  10. Final environmental impact statement. Management of commercially generated radioactive waste. Volume 1 of 3

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

    Not Available

    1980-10-01

    This EIS analyzes the significant environmental impacts that could occur if various technologies for management and disposal of high-level and transuranic wastes from commercial nuclear power reactors were to be developed and implemented. This EIS will serve as the environmental input for the decision on which technology, or technologies, will be emphasized in further research and development activities in the commercial waste management program. The action proposed in this EIS is to (1) adopt a national strategy to develop mined geologic repositories for disposal of commercially generated high-level and transuranic radioactive waste (while continuing to examine subseabed and very deepmore » hole disposal as potential backup technologies) and (2) conduct a R and D program to develop such facilities and the necessary technology to ensure the safe long-term containment and isolation of these wastes. The Department has considered in this statement: development of conventionally mined deep geologic repositories for disposal of spent fuel from nuclear power reactors and/or radioactive fuel reprocessing wastes; balanced development of several alternative disposal methods; and no waste disposal action. This EIS reflects the public review of and comments offered on the draft statement. Included are descriptions of the characteristics of nuclear waste, the alternative disposal methods under consideration, and potential environmental impacts and costs of implementing these methods. Because of the programmatic nature of this document and the preliminary nature of certain design elements assumed in assessing the environmental consequences of the various alternatives, this study has been based on generic, rather than specific, systems. At such time as specific facilities are identified for particular sites, statements addressing site-specific aspects will be prepared for public review and comment.« less

  11. Updating irradiated graphite disposal: Project 'GRAPA' and the international decommissioning network.

    PubMed

    Wickham, Anthony; Steinmetz, Hans-Jürgen; O'Sullivan, Patrick; Ojovan, Michael I

    2017-05-01

    Demonstrating competence in planning and executing the disposal of radioactive wastes is a key factor in the public perception of the nuclear power industry and must be demonstrated when making the case for new nuclear build. This work addresses the particular waste stream of irradiated graphite, mostly derived from reactor moderators and amounting to more than 250,000 tonnes world-wide. Use may be made of its unique chemical and physical properties to consider possible processing and disposal options outside the normal simple classifications and repository options for mixed low or intermediate-level wastes. The IAEA has an obvious involvement in radioactive waste disposal and has established a new project 'GRAPA' - Irradiated Graphite Processing Approaches - to encourage an international debate and collaborative work aimed at optimising and facilitating the treatment of irradiated graphite. Copyright © 2017 Elsevier Ltd. All rights reserved.

  12. Associate Directorate Environmental Management Infrastructure Plan for Area G and Area L Domes

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

    Stevens, Patrice Ann; Baumer, Andrew Ronald

    Technical Area 54, at Los Alamos National Laboratory (LANL) is situated in the east-central portion of the Laboratory on the Mesita del Buey between Pajarito Canyon to the south and Cañada del Buey to the north. TA-54 includes four MDAs designated as G, H, J, and L; a waste characterization, container storage, and transfer facility; active TRU waste and MLLW waste storage and low-level waste (LLW) disposal operations at Area G; active hazardous and mixed low-level (MLLW) waste storage operations at Area L; and administrative and support areas. MDA J has previously under-gone closure. Area G is a waste managementmore » and disposal area, used for the disposal and storage of radioactive wastes since 1957. Since August 2015, Area G has been in warm standby and provides minimal operations to support safety, compliance, and nitrate salt remediation. Located within Area G, MDA G covers 63-acres. MDA G contains 334 active and inactive waste management units, which include 36 pits, 294 shafts, and 4 trenches. In 1971, Area G began use for the retrievable storage of TRU waste. There are two pits, four trenches and 60 shafts that contain retrievable TRU waste. Thirty-three of the shafts contain TRU waste that may present unique problems for retrieval. In 1986, segregation of MLLW was initiated at Area G for treatment and temporary storage or for off-site disposal. Area G is the only active LLW disposal facility at the Laboratory. Current operations at Area G include storage and characterization of TRU and mixed TRU waste destined for off-site disposal at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico and the storage of MLLW destined for off-site treatment and/or disposal. Several above-ground container storage units (CSUs) are currently used for storage of containerized MLLW and/or mixed TRU wastes. These consist of asphalt pads and associated fabric domes or other structures. As defined by the Consent Order, MDA G contains 229 of the 334 subsurface waste management units at Area G. These MDA G disposal units include 32 pits, 193 shafts, and 4 trenches and contain LLW, MLLW and TRU waste. The remaining 105 solid waste management units (SWMUs) include RCRA-regulated landfill and storage units and DOE-regulated LLW disposal units. The TA-54 closure project must ensure that continuing waste operations at Area G and their transition to an interim or enduring facility are coordinated with closure activities.« less

  13. Special Analysis of Transuranic Waste in Trench T04C at the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nye County, Nevada, Revision 1

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

    Greg Shott, Vefa Yucel, Lloyd Desotell

    2008-05-01

    This Special Analysis (SA) was prepared to assess the potential impact of inadvertent disposal of a limited quantity of transuranic (TRU) waste in classified Trench 4 (T04C) within the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS). The Area 5 RWMS is a low-level radioactive waste disposal site in northern Frenchman Flat on the Nevada Test Site (NTS). The Area 5 RWMS is regulated by the U.S. Department of Energy (DOE) under DOE Order 435.1 and DOE Manual (DOE M) 435.1-1. The primary objective of the SA is to evaluate if inadvertent disposal of limitedmore » quantities of TRU waste in a shallow land burial trench at the Area 5 RWMS is in compliance with the existing, approved Disposal Authorization Statement (DAS) issued under DOE M 435.1-1. In addition, supplemental analyses are performed to determine if there is reasonable assurance that the requirements of Title 40, Code of Federal Regulations (CFR), Part 191, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes, can be met. The 40 CFR 191 analyses provide supplemental information regarding the risk to human health and the environment of leaving the TRU waste in T04C. In 1989, waste management personnel reviewing classified materials records discovered that classified materials buried in trench T04C at the Area 5 RWMS contained TRU waste. Subsequent investigations determined that a total of 102 55-gallon drums of TRU waste from Rocky Flats were buried in trench T04C in 1986. The disposal was inadvertent because unclassified records accompanying the shipment indicated that the waste was low-level. The exact location of the TRU waste in T04C was not recorded and is currently unknown. Under DOE M 435.1-1, Chapter IV, Section P.5, low-level waste disposal facilities must obtain a DAS. The DAS specifies conditions that must be met to operate within the radioactive waste management basis, consisting of a performance assessment (PA), composite analysis (CA), closure plan, monitoring plan, waste acceptance criteria, and a PA/CA maintenance plan. The DOE issued a DAS for the Area 5 RWMS in 2000. The Area 5 RWMS DAS was, in part, based on review of a CA as required under DOE M 435.1-1, Chapter IV, Section P.(3). A CA is a radiological assessment required for DOE waste disposed before 26 September 1988 and includes the radiological dose from all sources of radioactive material interacting with all radioactive waste disposed at the Area 5 RWMS. The approved Area 5 RWMS CA, which includes the inventory of TRU waste in T04C, indicates that the Area 5 RWMS waste inventory and all interacting sources of radioactive material can meet the 0.3 mSv dose constraint. The composite analysis maximum annual dose for a future resident at the Area 5 RWMS was estimated to be 0.01 mSv at 1,000 years. Therefore, the inadvertent disposal of TRU in T04C is protective of the public and the environment, and compliant with all the applicable requirements in DOE M 435.1-1 and the DAS. The U.S. Environmental Protection Agency promulgated 40 CFR 191 to establish standards for the planned disposal of spent nuclear fuel, high level, and transuranic wastes in geologic repositories. Although not required, the National Nuclear Security Administration Nevada Site Office requested a supplemental analysis to evaluate the likelihood that the inadvertent disposal of TRU waste in T04C meets the requirements of 40 CFR 191. The SA evaluates the likelihood of meeting the 40 CFR 191 containment requirements (CRs), assurance requirements, individual protection requirements (IPRs), and groundwater protection standards. The results of the SA indicate that there is a reasonable expectation of meeting all the requirements of 40 CFR 191. The conclusion of the SA is that the Area 5 RWMS with the TRU waste buried in T04C is in compliance with all requirements in DOE M 435.1-1 and the DAS. Compliance with the DAS is demonstrated by the results of the Area 5 RWMS CA. Supplemental analyses in the SA indicate there is a reasonable expectation that the TRU in T04C can meet all the requirements of 40 CFR 191. Therefore, inadvertent disposal of a limited quantity of TRU in a shallow land burial trench at the Area 5 RWMS does not pose a significant risk to the public and the environment.« less

  14. Development of a remote spectroelectrochemical sensor for technetium as pertechnetate

    NASA Astrophysics Data System (ADS)

    Monk, David James

    Subsurface contamination by technetium (Tc) is of particular concern in the monitoring, characterization, and remediation of underground nuclear waste storage tanks, processing areas, and associated surroundings at the Hanford Site and other U.S. DOE sites nationwide. The concern over this radioactive element arises for two reasons. First, its most common isotope, 99Tc, has an extremely long lifetime of 2.15 x 105 years. Second, it's most common chemical form in environmental conditions, pertechnetate (TcO4-), exhibits very fast migration through soils and readily presents itself to any nearby aquifer. Standard procedures of sampling and analysis in a laboratory prove to be slow and costly in the case of subsurface contamination by radioactive materials. It is highly desirable to develop sensors for these materials that possess the capability of either in-situ or on-site placement for continuous monitoring or immediate analysis of collected samples. These sensors need to possess adequate detection limit and selectivity, rapid response, reversibility (many measurements with one sensor), the ability to perform remotely, and ruggedness. This dissertation describes several areas of the continued work toward a sensor for 99Tc as TcO4-. Research initially focused on developing spectroelectrochemical instrumentation and a disposable sensing element, engineered to address the need to perform remote measurements. The instrument was then tested using samples containing 99Tc, resulting in the development of ancillary equipment and techniques to address concerns associated with performing experiments on radioactive materials. In these tests, the electrochemistry of TcO4 - was demonstrated to be irreversible. Electrochemical reduction of TcO4- on a bare or polymer modified electrode resulted in the continuous build up of technetium oxide (TcO2) on the electrode surface. This TcO2 formed in visual quantities in these films during electrochemistry, and proved to be non-ideal for spectroelectrochemical sensing. In the most recent work described, the development of metal templating techniques using complexes synthesized with rhenium (Re) was investigated as one means to circumvent this irreversibility. In an extension of the metal templating research, custom ligands were being designed which will impart structural rigidity and fluorescence to the template complexes, to facilitate selectivity and sensitivity at levels previously unprecedented for optical techniques.

  15. Low-level radioactive waste disposal. Study of a conceptual nuclear energy center at Green River, Utah

    NASA Astrophysics Data System (ADS)

    Card, D. H.; Hunter, P. H.; Barg, D.; Desouza, F.; Felthauser, K.; Winkler, V.; White, R.

    1982-02-01

    The ramifications of constructing a nuclear energy center in an arid western region were studied. The alternatives for disposing of the low level waste on the site are compared with the alternative of transporting the waste to the nearest commercial waste disposal site for permanent disposal. Both radiological and nonradiological impacts on the local socioeconomic infrastructure and the environment are considered. Disposal on the site was found to cost considerably less than off site disposal with only negligible impacts associated with the disposal option on either mankind or the environment.

  16. Rapid immobilization of simulated radioactive soil waste by microwave sintering.

    PubMed

    Zhang, Shuai; Shu, Xiaoyan; Chen, Shunzhang; Yang, Huimin; Hou, Chenxi; Mao, Xueli; Chi, Fangting; Song, Mianxin; Lu, Xirui

    2017-09-05

    A rapid and efficient method is particularly necessary in the timely disposal of seriously radioactive contaminated soil. In this paper, a series of simulated radioactive soil waste containing different contents of neodymium oxide (3-25wt.%) has been successfully vitrified by microwave sintering at 1300°C for 30min. The microstructures, morphology, element distribution, density and chemical durability of as obtained vitrified forms have been analyzed. The results show that the amorphous structure, homogeneous element distribution, and regular density improvement are well kept, except slight cracks emerge on the magnified surface for the 25wt.% Nd 2 O 3 -containing sample. Moreover, all the vitrified forms exhibit excellent chemical durability, and the leaching rates of Nd are kept as ∼10 -4 -10 -6 g/(m 2 day) within 42days. This demonstrates a potential application of microwave sintering in radioactive contaminated soil disposal. Copyright © 2017 Elsevier B.V. All rights reserved.

  17. Remote-Handled Low-Level Waste Disposal Project Code of Record

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

    Austad, S. L.; Guillen, L. E.; McKnight, C. W.

    2015-04-01

    The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by themore » Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.« less

  18. Characteristics and Classification of Solid Radioactive Waste From the Front-End of the Uranium Fuel Cycle.

    PubMed

    Liu, Xinhua; Wei, Fangxin; Xu, Chunyan; Liao, Yunxuan; Jiang, Jing

    2015-09-01

    The proper classification of radioactive waste is the basis upon which to define its disposal method. In view of differences between waste containing artificial radionuclides and waste with naturally occurring radionuclides, the scientific definition of the properties of waste arising from the front end of the uranium fuel cycle (UF Waste) is the key to dispose of such waste. This paper is intended to introduce briefly the policy and practice to dispose of such waste in China and some foreign countries, explore how to solve the dilemma facing such waste, analyze in detail the compositions and properties of such waste, and finally put forward a new concept of classifying such waste as waste with naturally occurring radionuclides.

  19. Well-construction and hydrogeologic data for observation wells in the vicinity of a low-level radioactive-waste disposal site near Sheffield, Illinois

    USGS Publications Warehouse

    Mansue, Lawrence J.; Mills, Patrick C.

    1991-01-01

    The U.S. Geological Survey conducted hydrogeologic studies at the low-level radioactive-waste disposal site near Sheffield, Illinois, from 1976 through 1987. During that period, 108 observation wells were installed in the vicinity of the disposal site in glacial and post-glacial deposits of Quaternary age and bedrock of Pennsylvanian age. Data in this report include the location of each well, the date each well was drilled, the geologic units penetrated by each well, the physical measurements of each well, the elevations of the top (measuring point) of each well and geologic-unit contacts at each well, and the highest and lowest recorded water levels in each well.

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

    S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.

    The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by themore » Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.« less

  1. CEM V based special cementitious materials investigated by means of SANS method. Preliminary results

    NASA Astrophysics Data System (ADS)

    Dragolici, A. C.; Balasoiu, M.; Orelovich, O. L.; Ionascu, L.; Nicu, M.; Soloviov, D. V.; Kuklin, A. I.; Lizunov, E. I.; Dragolici, F.

    2017-05-01

    The management of the radioactive waste assume the conditioning in a cement matrix as an embedding, stable, disposal material. Cement matrix is the first and most important engineering barrier against the migration in the environment of the radionuclides contained in the waste packages. Knowing how the microstructure develops is therefore desirable in order to assess the compatibility of radioactive streams with cement and predict waste form performance during storage and disposal. For conditioning wastes containing radioactive aluminum new formulas of low basicity cements, using coatings as a barrier between the metal and the conditioning environment or introducing a corrosion inhibitor in the matrix system are required. Preliminary microstructure investigation of such improved CEM V based cement matrix is reported.

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

    Kot, Wing K.; Pegg, Ian L.; Brandys, Marek

    One of the primary roles of waste pretreatment at the Hanford Tank Waste Treatment and Immobilization Plant (WTP) is to separate the majority of the radioactive components from the majority of the nonradioactive components in retrieved tank wastes, producing a high level waste (HLW) stream and a low activity waste (LAW) stream. This separation process is a key element in the overall strategy to reduce the volume of HLW that requires vitrification and subsequent disposal in a national deep geological repository for high level nuclear waste. After removal of the radioactive constituents, the LAW stream, which has a much largermore » volume but smaller fraction of radioactivity than the HLW stream, will be immobilized and disposed of in near surface facilities at the Hanford site.« less

  3. Current Situation for Management of Disused Sealed Radioactive Sources in Japan - 13025

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

    Kusama, Keiji; Miyamoto, Yoichi

    2013-07-01

    As for the Sealed Radioactive Source currently used in Japan, many of them are imported from overseas. The U.S., Canada, Germany, the Netherlands, Belgium and Czech Republic are the main exporting States. Many of disused sealed radioactive sources are being returned to exporting States. The sealed radioactive sources which cannot be returned to exporting States are appropriately kept in the domestic storage facility. So, there are not main problem on the long term management of disused sealed radioactive sources in Japan. However, there are some difficulties on repatriate. One is reservation of a means of transport. The sea mail whichmore » conveys radioactive sources owing to reduction of movement of international cargo is decreasing in number. And there is a denial of shipment. Other one is that the manufacturer has already resigned from the work and cannot return disused sealed radioactive sources, or a manufacturer cannot specify and disused sources cannot be returned. The disused sealed radioactive source which cannot be repatriated is a little in term of radioactivity. As for the establishment of national measure of final disposal facility for disused sealed radioactive sources, in Japan, it is not yet installed with difficulty. Since there are many countries for which installation of a final disposal facility for disused sealed radioactive sources is difficult, the source manufacture country should respond positively to return the source which was manufactured and sold in the past. (authors)« less

  4. 25 Years Of Environmental Remediation In The General Separations Area Of The Savannah River Site: Lessons Learned About What Worked And What Did Not Work In Soil And Groundwater Cleanup

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

    Blount, Gerald; Thibault, Jeffrey; Millings, Margaret

    The Savannah River Site (SRS) is owned and administered by the US Department of Energy (DOE). SRS covers an area of approximately 900 square kilometers. The General Separation Area (GSA) is located roughly in the center of the SRS and includes: radioactive material chemical separations facilities, radioactive waste tank farms, a variety of radioactive seepage basins, and the radioactive waste burial grounds. Radioactive wastes were disposed in the GSA from the mid-1950s through the mid-1990s. Radioactive operations at the F Canyon began in 1954; radioactive operations at H Canyon began in 1955. Waste water disposition to the F and Hmore » Seepage Basins began soon after operations started in the canyons. The Old Radioactive Waste Burial Ground (ORWBG) began operations in 1952 to manage solid waste that could be radioactive from all the site operations, and ceased receiving waste in 1972. The Mixed Waste Management Facility (MWMF) and Low Level Radioactive Waste Disposal Facility (LLRWDF) received radioactive solid waste from 1969 until 1995. Environmental legislation enacted in the 1970s, 1980s, and 1990s led to changes in waste management and environmental cleanup practices at SRS. The US Congress passed the Clean Air Act in 1970, and the Clean Water Act in 1972; the Resource Conservation and Recovery Act (RCRA) was enacted in 1976; the Comprehensive Environmental Response Compensation, and Liability Act (CERCLA) was enacted by Congress in 1980; the Federal Facilities Compliance Act (FFCA) was signed into law in 1992. Environmental remediation at the SRS essentially began with a 1987 Settlement Agreement between the SRS and the State of South Carolina (under the South Carolina Department of Health and Environmental Control - SCDHEC), which recognized linkage between many SRS waste management facilities and RCRA. The SRS manages several of the larger groundwater remedial activities under RCRA for facilities recognized early on as environmental problems. All subsequent environmental remediation projects tend to be managed under tri-party agreement (DOE, Environmental Protection Agency, and SCDHEC) through the Federal Facilities Agreement. During 25 years of environmental remediation SRS has stabilized and capped seepage basins, and consolidated and capped waste units and burial grounds in the GSA. Groundwater activities include: pump and treat systems in the groundwater, installation of deep subsurface barrier systems to manage groundwater flow, in situ chemical treatments in the groundwater, and captured contaminated groundwater discharges at the surface for management in a forest irrigation system. Over the last 25 years concentrations of contaminants in the aquifers beneath the GSA and in surface water streams in the GSA have dropped significantly. Closure of 65 waste sites and 4 RCRA facilities has been successfully accomplished. Wastes have been successfully isolated in place beneath a variety of caps and cover systems. Environmental clean-up has progressed to the stage where most of the work involves monitoring, optimization, and maintenance of existing remedial systems. Many lessons have been learned in the process. Geotextile covers outperform low permeability clay caps, especially with respect to the amount of repairs required to upkeep the drainage layers as the caps age. Passive, enhanced natural processes to address groundwater contamination are much more cost effective than pump and treat systems. SRS operated two very large pump and treat systems at the F and H Seepage Basins to attempt to limit the release of tritium to Fourmile Branch, a tributary of the Savannah River. The systems were designed to extract contaminated acidic groundwater, remove all contamination except tritium (not possible to remove the tritium from the water), and inject the tritiated groundwater up-gradient of the source area and the plume. The concept was to increase the travel time of the injected water for radioactive decay of the tritium. The two systems were found to be non-effective and potentially mobilizing more contamination. SRS invested approximately $50 million in construction and approximately $100 million in 6 years of operation. The H Seepage Basin pump and treat system was replaced by a series of subsurface barriers that alters the groundwater velocity; the F Seepage Basin pump and treat system was replaced by subsurface barriers forming a funnel and gate augmented by chemical treatment within the gates. These replacement systems are mostly passive and cost approximately $13 million to construct, and have reduced the tritium flux to Fourmile Branch, in these plumes, by over 70%. SRS manages non-acidic tritiated groundwater releases to Fourmile Branch from the southwest plume of the MWMF with a forest irrigation system. Tritiated water is captured with a sheetpile dam below the springs that caused releases to Fourmile Branch. Water from the irrigation pond is pumped to a filter plant prior to irrigation of approximately 26 hectares of mixed forest and developing pine plantation. SRS has almost achieved a 70% reduction in tritium flux to the Branch from this plume. The system cost approximately $5 million to construct with operation cost of approximately $500K per year. In conclusion, many lessons have been learned in 25 years of relatively aggressive remedial activities in the GSA. Geotextile covers outperform low permeability clay caps, especially with respect to the amount of repairs required to upkeep the drainage layers as the caps age. Passive, enhanced natural processes to address groundwater contamination are much more cost effective than pump and treat systems. In water management situations with non-accumulative contaminants (tritium, VOCs, etc.) irrigation in a forest setting can be very effective.« less

  5. DWPF Safely Dispositioning Liquid Waste

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

    None

    2016-01-05

    The only operating radioactive waste glassification plant in the nation, the Defense Waste Processing Facility (DWPF) converts the liquid radioactive waste currently stored at the Savannah River Site (SRS) into a solid glass form suitable for long-term storage and disposal. Scientists have long considered this glassification process, called “vitrification,” as the preferred option for treating liquid radioactive waste.

  6. Risk-informed radioactive waste classification and reclassification.

    PubMed

    Croff, Allen G

    2006-11-01

    Radioactive waste classification systems have been developed to allow wastes having similar hazards to be grouped for purposes of storage, treatment, packaging, transportation, and/or disposal. As recommended in the National Council on Radiation Protection and Measurements' Report No. 139, Risk-Based Classification of Radioactive and Hazardous Chemical Wastes, a preferred classification system would be based primarily on the health risks to the public that arise from waste disposal and secondarily on other attributes such as the near-term practicalities of managing a waste, i.e., the waste classification system would be risk informed. The current U.S. radioactive waste classification system is not risk informed because key definitions--especially that of high-level waste--are based on the source of the waste instead of its inherent characteristics related to risk. A second important reason for concluding the existing U.S. radioactive waste classification system is not risk informed is there are no general principles or provisions for exempting materials from being classified as radioactive waste which would then allow management without regard to its radioactivity. This paper elaborates the current system for classifying and reclassifying radioactive wastes in the United States, analyzes the extent to which the system is risk informed and the ramifications of its not being so, and provides observations on potential future direction of efforts to address shortcomings in the U.S. radioactive waste classification system as of 2004.

  7. Problems associated with the disposal of radioactive wastes in the sea (in French)

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

    Ancellin, J.

    1973-06-01

    The disposal of radioactive wastes in the sea (case of the La Hague site) is favored by the physical dispersion and transport of the effluents by marine currents. Concentration and precipitation phenomena can inhibit the dispersion. Research has been effected on the way in which the fixing of pollutants occurs and the degree to which it occurs. Investigations were then carried out on the utilization of the marine environment by man (foodstuffs from the sea, distribution of such products, alimentation, critical population groups). (FR)

  8. Radioactive waste material disposal

    DOEpatents

    Forsberg, C.W.; Beahm, E.C.; Parker, G.W.

    1995-10-24

    The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide. 3 figs.

  9. Radioactive waste material disposal

    DOEpatents

    Forsberg, Charles W.; Beahm, Edward C.; Parker, George W.

    1995-01-01

    The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide.

  10. Model tracking system for low-level radioactive waste disposal facilities: License application interrogatories and responses

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

    Benbennick, M.E.; Broton, M.S.; Fuoto, J.S.

    This report describes a model tracking system for a low-level radioactive waste (LLW) disposal facility license application. In particular, the model tracks interrogatories (questions, requests for information, comments) and responses. A set of requirements and desired features for the model tracking system was developed, including required structure and computer screens. Nine tracking systems were then reviewed against the model system requirements and only two were found to meet all requirements. Using Kepner-Tregoe decision analysis, a model tracking system was selected.

  11. Method for making a low density polyethylene waste form for safe disposal of low level radioactive material

    DOEpatents

    Colombo, P.; Kalb, P.D.

    1984-06-05

    In the method of the invention low density polyethylene pellets are mixed in a predetermined ratio with radioactive particulate material, then the mixture is fed through a screw-type extruder that melts the low density polyethylene under a predetermined pressure and temperature to form a homogeneous matrix that is extruded and separated into solid monolithic waste forms. The solid waste forms are adapted to be safely handled, stored for a short time, and safely disposed of in approved depositories.

  12. The characterization and risk assessment of the `Red Forest` radioactive waste burial site at Chernobyl Nuclear Power Plant

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

    Bungai, D.A.; Skalskij, A.S.; Dzhepo, S.P.

    The `Red Forest` radioactive waste burials created during emergency clean-up activities at Chernobyl Nuclear Power Plant represent a serious source of radioactive contamination of the local ground water system with 9OSr concentration in ground water exceeding the drinking water standard by 3-4 orders of magnitude. In this paper we present results of our hydrogeological and radiological `Red Forest` site characterization studies, which allow us to estimate 9OSr subsurface migration parameters. We use then these parameters to assess long terrain radionuclide transport to groundwater and surface water, and to analyze associated health risks. Our analyses indicate that 9OSr transport via groundmore » water pathway from `Red Forest` burials to the adjacent Pripyat River is relatively insignificant due to slow release of 9OSr from the waste burials (less than 1% of inventory per year) and due to long enough ground water residence time in the subsurface, which allows substantial decay of the radioactive contaminant. Tins result and our previous analyses indicate, that though conditions of radioactive waste storage in burials do not satisfy Ukrainian regulation on radiation protection, health risks caused by radionuclide migration to ground water from `Red Forest` burials do not justify application of expensive countermeasures.« less

  13. Radioactive Waste.

    ERIC Educational Resources Information Center

    Blaylock, B. G.

    1978-01-01

    Presents a literature review of radioactive waste disposal, covering publications of 1976-77. Some of the studies included are: (1) high-level and long-lived wastes, and (2) release and burial of low-level wastes. A list of 42 references is also presented. (HM)

  14. MANAGING UNCERTAINTIES ASSOCIATED WITH RADIOACTIVE WASTE DISPOSAL: TASK GROUP 4 OF THE IAEA PRISM PROJECT

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

    Seitz, R.

    2011-03-02

    It is widely recognized that the results of safety assessment calculations provide an important contribution to the safety arguments for a disposal facility, but cannot in themselves adequately demonstrate the safety of the disposal system. The safety assessment and a broader range of arguments and activities need to be considered holistically to justify radioactive waste disposal at any particular site. Many programs are therefore moving towards the production of what has become known as a Safety Case, which includes all of the different activities that are conducted to demonstrate the safety of a disposal concept. Recognizing the growing interest inmore » the concept of a Safety Case, the International Atomic Energy Agency (IAEA) is undertaking an intercomparison and harmonization project called PRISM (Practical Illustration and use of the Safety Case Concept in the Management of Near-surface Disposal). The PRISM project is organized into four Task Groups that address key aspects of the Safety Case concept: Task Group 1 - Understanding the Safety Case; Task Group 2 - Disposal facility design; Task Group 3 - Managing waste acceptance; and Task Group 4 - Managing uncertainty. This paper addresses the work of Task Group 4, which is investigating approaches for managing the uncertainties associated with near-surface disposal of radioactive waste and their consideration in the context of the Safety Case. Emphasis is placed on identifying a wide variety of approaches that can and have been used to manage different types of uncertainties, especially non-quantitative approaches that have not received as much attention in previous IAEA projects. This paper includes discussions of the current results of work on the task on managing uncertainty, including: the different circumstances being considered, the sources/types of uncertainties being addressed and some initial proposals for approaches that can be used to manage different types of uncertainties.« less

  15. Studies concerning the durability of concrete vaults for intermediate level radioactive waste disposal: Electrochemical monitoring and corrosion aspects

    NASA Astrophysics Data System (ADS)

    Duffó, G. S.; Farina, S. B.; Arva, E. A.; Giordano, C. M.; Lafont, C. J.

    2006-11-01

    The Argentine Atomic Energy Commission (CNEA) is responsible of the development of a management nuclear waste disposal programme. This programme contemplates the design and construction of a facility for the final disposal of intermediate-level radioactive waste. The proposed concept is the near-surface monolithic repository similar to those in operation in El Cabril, Spain. The design of this type of repository is based on the use of multiple, independent and redundant barriers. Since the vault and cover are major components of the engineered barriers, the durability of these concrete structures is an important aspect for the facilities integrity. This work presents a laboratory and field investigation performed for the last 6 years on reinforced concrete specimens, in order to predict the service life of the intermediate level radioactive waste disposal vaults from data obtained from electrochemical techniques. On the other hand, the development of sensors that allow on-line measurements of rebar corrosion potential and corrosion current density; incoming oxygen flow that reaches the metal surface; concrete electrical resistivity and chloride concentration is shown. Those sensors, properly embedded in a new full scale vault (nowadays in construction), will allow the monitoring of the corrosion process of the steel rebars embedded in thestructure.

  16. Release and disposal of materials during decommissioning of Siemens MOX fuel fabrication plant at Hanau, Germany

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

    Koenig, Werner; Baumann, Roland

    2007-07-01

    In September 2006, decommissioning and dismantling of the Siemens MOX Fuel Fabrication Plant in Hanau were completed. The process equipment and the fabrication buildings were completely decommissioned and dismantled. The other buildings were emptied in whole or in part, although they were not demolished. Overall, the decommissioning process produced approximately 8500 Mg of radioactive waste (including inactive matrix material); clearance measurements were also performed for approximately 5400 Mg of material covering a wide range of types. All the equipment in which nuclear fuels had been handled was disposed of as radioactive waste. The radioactive waste was conditioned on the basismore » of the requirements specified for the projected German final disposal site 'Schachtanlage Konrad'. During the pre-conditioning, familiar processes such as incineration, compacting and melting were used. It has been shown that on account of consistently applied activity containment (barrier concept) during operation and dismantling, there has been no significant unexpected contamination of the plant. Therefore almost all the materials that were not a priori destined for radioactive waste were released without restriction on the basis of the applicable legal regulations (chap. 29 of the Radiation Protection Ordinance), along with the buildings and the plant site. (authors)« less

  17. 10 CFR 60.71 - Records and reports.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN GEOLOGIC REPOSITORIES Records... the Energy Reorganization Act. (b) Records of the receipt, handling, and disposition of radioactive waste at a geologic repository operations area shall contain sufficient information to provide a...

  18. Radioactive waste management in Poland status and strategy for the future

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

    Wlodarski, J.

    1995-12-01

    Site selection for a new radioactive waste repository in Poland has been started. The repository will contain low- and intermediate-level radioactive wastes and spent fuel. Superficial, shallow underground and deep underground disposal options were considered; 39 potential sites have been selected. Issues to be resolved regarding waste management in Poland are also outlined in this paper.

  19. DWPF Safely Dispositioning Liquid Waste

    ScienceCinema

    None

    2018-06-21

    The only operating radioactive waste glassification plant in the nation, the Defense Waste Processing Facility (DWPF) converts the liquid radioactive waste currently stored at the Savannah River Site (SRS) into a solid glass form suitable for long-term storage and disposal. Scientists have long considered this glassification process, called “vitrification,” as the preferred option for treating liquid radioactive waste.

  20. Investigations of the unsaturated zone at two radioactive waste disposal sites in Lithuania.

    PubMed

    Skuratovič, Žana; Mažeika, Jonas; Petrošius, Rimantas; Martma, Tõnu

    2016-01-01

    The unsaturated zone is an important part of the water cycle, governed by many hydrological and hydrogeological factors and processes and provide water and nutrients to the terrestrial ecosystem. Besides, the soils of the unsaturated zone are regarded as the first natural barrier to a large extent and are able to limit the spread of contaminants depending on their properties. The unsaturated zone provides a linkage between atmospheric moisture, groundwater, and seepage of groundwater to streams, lakes, or other surface water bodies. The major difference between water flow in saturated and unsaturated soils is that the hydraulic conductivity, which is conventionally assumed to be a constant in saturated soils, is a function of the degree of saturation or matrix suction in the unsaturated soils. In Lithuania, low and intermediate level radioactive wastes generated from medicine, industry and research were accumulated at the Maisiagala radioactive waste repository. Short-lived low and intermediate levels radioactive waste, generated during the operation of the Ignalina Nuclear Power Plant (INPP) and arising after the INPP decommissioning will be disposed of in the near surface repository close to the INPP (Stabatiske site). Extensive data sets of the hydraulic properties and water content attributed to unsaturated zone soil profiles of the two radioactive waste disposal sites have been collected and summarized. Globally widespread radionuclide tritium ((3)H) and stable isotope ratio ((18)O/(16)O and (2)H/(1)H) distribution features were determined in precipitation, unsaturated zone soil moisture profiles and groundwater.

  1. Site environmental report for calendar year 2002. DOE operations at the Boeing Company, Rocketdyne Propulsion and Power

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

    None

    2003-09-30

    This Annual Site Environmental Report (ASER) for 2002 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing' s Santa Susana Field Laboratory (SSFL)). In the past, the Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations at ETEC included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities at ETEC involved the operation of large-scale liquid metal facilities that were used for testing liquid metal fast breeder components. All nuclear work was terminated in 1988, and,more » subsequently, all radiological work has been directed toward decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Closure of the liquid metal test facilities began in 1996. Results of the radiological monitoring program for the calendar year 2002 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property ( land, structures, waste), and recycling. All radioactive w astes are processed for disposal at DOE disposal sites and/or other licensed sites approved by DOE for radioactive waste disposal. No liquid radioactive wastes are released into the environment, and no structural debris from buildings w as transferred to municipal landfills or recycled in 2002.« less

  2. Safe disposal of surplus plutonium

    NASA Astrophysics Data System (ADS)

    Gong, W. L.; Naz, S.; Lutze, W.; Busch, R.; Prinja, A.; Stoll, W.

    2001-06-01

    About 150 tons of weapons grade and weapons usable plutonium (metal, oxide, and in residues) have been declared surplus in the USA and Russia. Both countries plan to convert the metal and oxide into mixed oxide fuel for nuclear power reactors. Russia has not yet decided what to do with the residues. The US will convert residues into a ceramic, which will then be over-poured with highly radioactive borosilicate glass. The radioactive glass is meant to provide a deterrent to recovery of plutonium, as required by a US standard. Here we show a waste form for plutonium residues, zirconia/boron carbide (ZrO 2/B 4C), with an unprecedented combination of properties: a single, radiation-resistant, and chemically durable phase contains the residues; billion-year-old natural analogs are available; and criticality safety is given under all conceivable disposal conditions. ZrO 2/B 4C can be disposed of directly, without further processing, making it attractive to all countries facing the task of plutonium disposal. The US standard for protection against recovery can be met by disposal of the waste form together with used reactor fuel.

  3. (US low-level radioactive waste management facility design, construction, and operation): Foreign trip report, July 22--30, 1989

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

    Van Hoesen, S.D.; Bolinsky, J.

    1989-08-02

    The Martin Marietta Energy Systems, Inc., Team, consisting of representatives of the Engineering Division and Oak Ridge National Laboratory (ORNL), participated in a technology exchange program on French and US low-level radioactive waste (LLW) management facility design, construction, and operation. Meetings were held at the Agence National pour la Gestion des Dechets Radioactif (ANDRA) offices in Paris to review the designs for the new French LLW disposal facility, the Cente de Stockage de l'Aube (CSA), and the new ORNL LLW disposal project, the Interim Waste Management Facility (IWMF), and the results of the French LLW disposal facility cover experiment atmore » St. Sauveur. Visits were made to the operating LLW disposal facility, the Centre de Stockage de la Manche (CSM), the LLW conditioning facilities at the La Hague Reprocessing Facility, and the St. Saueveur Disposal Cap Experiment to discuss design, construction, and operating experience. A visit was also made to the CSA site to view the progress made in construction of the new facility.« less

  4. Space disposal of nuclear wastes. Volume 1: Socio-political aspects

    NASA Technical Reports Server (NTRS)

    Laporte, T.; Rochlin, G. I.; Metlay, D.; Windham, P.

    1976-01-01

    The history and interpretation of radioactive waste management in the U.S., criteria for choosing from various options for waste disposal, and the impact of nuclear power growth from 1975 to 2000 are discussed. Preconditions for the existence of high level wastes in a form suitable for space disposal are explored. The role of the NASA space shuttle program in the space disposal of nuclear wastes, and the impact on program management, resources and regulation are examined.

  5. Performance assessment for continuing and future operations at solid waste storage area 6

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

    NONE

    1997-09-01

    This revised performance assessment (PA) for the continued disposal operations at Solid Waste Storage Area (SWSA) 6 on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the performance objectives for low-level radioactive waste (LLW) disposal contained in the US Department of Energy (DOE) Order 5820.2A. This revised PA considers disposal operations conducted from September 26, 1988, through the projects lifetime of the disposal facility.

  6. Site characterization for LIL radioactive waste disposal in Romania

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

    Diaconu, D. R.; Birdsell, K. H.; Witkowski, M. S.

    2001-01-01

    Recent studies in radioactive waste management in Romania have focussed mainly on the disposal of low and intermediate level waste from the operation of the new nuclear power plant at Cernavoda. Following extensive geological, hydrological, seismological, physical and chemical investigations, a disposal site at Saligny has been selected. This paper presents description of the site at Saligny as well as the most important results of the site characterisation. These are reflected in the three-dimensional, stratigraphical representation of the loess and clay layers and in representative parameter values for the main layers. Based on these data, the simulation of the background,more » unsaturated-zone water flow at the Saligny site, calculated by the FEHM code, is in a good agreement with the measured moisture profile.« less

  7. Earth to Moon Transfers - Direct vs Via Libration Points (L1, L2)

    NASA Technical Reports Server (NTRS)

    Condon, Gerald L.; Wilson, Sam

    2002-01-01

    Recommend Direct Remote Ocean Area impact disposal for caseswithout hazardous (e.g., radioactive) material on LTV kickstage Controlled Earth contact. Relatively small disposal AV. Avoids close encounter with Moon. Trajectories can be very sensitive to initial conditions (at disposalmaneuver).V to correct for errors is small. Recommend Heliocentric Orbit disposal for cases with hazardousmaterial on LTV kickstage. No Earth or Lunar disposal issues (e.g.. impact location, debris footprint,litter). Relatively low disposal AV cost. Further study required to determine possibility of re-contact with Earth.

  8. An overview of radioactive waste disposal procedures of a nuclear medicine department

    PubMed Central

    Ravichandran, R.; Binukumar, J. P.; Sreeram, Rajan; Arunkumar, L. S.

    2011-01-01

    Radioactive wastes from hospitals form one of the various types of urban wastes, which are managed in developed countries in a safe and organized way. In countries where growth of nuclear medicine services are envisaged, implementations of existing regulatory policies and guidelines in hospitals in terms of handling of radioactive materials used in the treatment of patients need a good model. To address this issue, a brief description of the methods is presented. A designed prototype waste storage trolley is found to be of great help in decaying the I-131 solid wastes from wards before releasing to waste treatment plant of the city. Two delay tanks with collection time of about 2 months and delay time of 2 months alternately result in 6 releases of urine toilet effluents to the sewage treatment plant (STP) of the hospital annually. Samples of effluents collected at releasing time documented radioactive releases of I-131 much below recommended levels of bi-monthly release. External counting of samples showed good statistical correlation with calculated values. An overview of safe procedures for radioactive waste disposal is presented. PMID:21731225

  9. An overview of radioactive waste disposal procedures of a nuclear medicine department.

    PubMed

    Ravichandran, R; Binukumar, J P; Sreeram, Rajan; Arunkumar, L S

    2011-04-01

    Radioactive wastes from hospitals form one of the various types of urban wastes, which are managed in developed countries in a safe and organized way. In countries where growth of nuclear medicine services are envisaged, implementations of existing regulatory policies and guidelines in hospitals in terms of handling of radioactive materials used in the treatment of patients need a good model. To address this issue, a brief description of the methods is presented. A designed prototype waste storage trolley is found to be of great help in decaying the I-131 solid wastes from wards before releasing to waste treatment plant of the city. Two delay tanks with collection time of about 2 months and delay time of 2 months alternately result in 6 releases of urine toilet effluents to the sewage treatment plant (STP) of the hospital annually. Samples of effluents collected at releasing time documented radioactive releases of I-131 much below recommended levels of bi-monthly release. External counting of samples showed good statistical correlation with calculated values. An overview of safe procedures for radioactive waste disposal is presented.

  10. THERMO-ELECTRIC GENERATOR

    DOEpatents

    Jordan, K.C.

    1958-07-22

    The conversion of heat energy into electrical energy by a small compact device is descrtbed. Where the heat energy is supplied by a radioactive material and thermopIIes convert the heat to electrical energy. The particular battery construction includes two insulating discs with conductive rods disposed between them to form a circular cage. In the center of the cage is disposed a cup in which the sealed radioactive source is located. Each thermopile is formed by connecting wires from two adjacent rods to a potnt on an annular ring fastened to the outside of the cup, the ring having insulation on its surface to prevent electrica1 contact with the thermopiles. One advantage of this battery construction is that the radioactive source may be inserted after the device is fabricated, reducing the radiation hazard to personnel assembling the battery.

  11. 10 CFR 61.43 - Protection of individuals during operations.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 61.43 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.43 Protection of individuals during operations. Operations at the land disposal facility must be conducted in compliance with the standards for radiation protection...

  12. 10 CFR 61.43 - Protection of individuals during operations.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 61.43 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.43 Protection of individuals during operations. Operations at the land disposal facility must be conducted in compliance with the standards for radiation protection...

  13. 10 CFR 61.43 - Protection of individuals during operations.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 61.43 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.43 Protection of individuals during operations. Operations at the land disposal facility must be conducted in compliance with the standards for radiation protection...

  14. 10 CFR 61.43 - Protection of individuals during operations.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 61.43 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.43 Protection of individuals during operations. Operations at the land disposal facility must be conducted in compliance with the standards for radiation protection...

  15. 10 CFR 61.43 - Protection of individuals during operations.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 61.43 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.43 Protection of individuals during operations. Operations at the land disposal facility must be conducted in compliance with the standards for radiation protection...

  16. Using Downhole Probes to Locate and Characterize Buried Transuranic and Mixed Low Level Waste

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

    Steinman, Donald K; Bramblett, Richard L; Hertzog, Russel C

    2012-06-25

    Borehole logging probes were developed and tested to locate and quantify transuranic elements in subsurface disposal areas and in contaminated sites at USDOE Weapons Complex sites. A new method of measuring very high levels of chlroine in the subsurface was developed using pulsed neutron technology from oilfield applications. The probes were demonstrated at the Hanford site in wells containing plutonium and other contaminants.

  17. Radiological risk assessment and biosphere modelling for radioactive waste disposal in Switzerland.

    PubMed

    Brennwald, M S; van Dorp, F

    2009-12-01

    Long-term safety assessments for geological disposal of radioactive waste in Switzerland involve the demonstration that the annual radiation dose to humans due to the potential release of radionuclides from the waste repository into the biosphere will not exceed the regulatory limit of 0.1 mSv. Here, we describe the simple but robust approach used by Nagra (Swiss National Cooperative for the Disposal of Radioactive Waste) to quantify the dose to humans as a result to time-dependent release of radionuclides from the geosphere into the biosphere. The model calculates the concentrations of radionuclides in different terrestrial and aquatic compartments of the surface environment. The fluxes of water and solids within the environment are the drivers for the exchange of radionuclides between these compartments. The calculated radionuclide concentrations in the biosphere are then used to estimate the radiation doses to humans due to various exposure paths (e.g. ingestion of radionuclides via drinking water and food, inhalation of radionuclides, external irradiation from radionuclides in soils). In this paper we also discuss recent new achievements and planned future work.

  18. Apparatus for the processing of solid mixed waste containing radioactive and hazardous materials

    DOEpatents

    Gotovchikov, Vitaly T.; Ivanov, Alexander V.; Filippov, Eugene A.

    1999-03-16

    Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination oaf plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter.

  19. Processing of solid mixed waste containing radioactive and hazardous materials

    DOEpatents

    Gotovchikov, Vitaly T.; Ivanov, Alexander V.; Filippov, Eugene A.

    1998-05-12

    Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter.

  20. Apparatus for the processing of solid mixed waste containing radioactive and hazardous materials

    DOEpatents

    Gotovchikov, V.T.; Ivanov, A.V.; Filippov, E.A.

    1999-03-16

    Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter. 6 figs.

  1. Processing of solid mixed waste containing radioactive and hazardous materials

    DOEpatents

    Gotovchikov, V.T.; Ivanov, A.V.; Filippov, E.A.

    1998-05-12

    Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter. 6 figs.

  2. A new technology for determining transport parameters in porous media

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

    Conca, J.L.; Wright, J.

    The UFA Method can directly and rapidly measure transport parameters for any porous medium over a wide range of water contents and conditions. UFA results for subsurface sediments at a mixed-waste disposal site at the Hanford Site in Washington State provided the data necessary for detailed hydrostratigraphic mapping, subsurface flux and recharge distributions, and subsurface chemical mapping. Seven hundred unsaturated conductivity measurements along with pristine pore water extractions were obtained in only six months using the UFA. These data are used to provide realistic information to conceptual models, predictive models and restoration strategies.

  3. Quantitative risk assessment of the New York State operated West Valley Radioactive Waste Disposal Area.

    PubMed

    Garrick, B John; Stetkar, John W; Bembia, Paul J

    2010-08-01

    This article is based on a quantitative risk assessment (QRA) that was performed on a radioactive waste disposal area within the Western New York Nuclear Service Center in western New York State. The QRA results were instrumental in the decision by the New York State Energy Research and Development Authority to support a strategy of in-place management of the disposal area for another decade. The QRA methodology adopted for this first of a kind application was a scenario-based approach in the framework of the triplet definition of risk (scenarios, likelihoods, consequences). The measure of risk is the frequency of occurrence of different levels of radiation dose to humans at prescribed locations. The risk from each scenario is determined by (1) the frequency of disruptive events or natural processes that cause a release of radioactive materials from the disposal area; (2) the physical form, quantity, and radionuclide content of the material that is released during each scenario; (3) distribution, dilution, and deposition of the released materials throughout the environment surrounding the disposal area; and (4) public exposure to the distributed material and the accumulated radiation dose from that exposure. The risks of the individual scenarios are assembled into a representation of the risk from the disposal area. In addition to quantifying the total risk to the public, the analysis ranks the importance of each contributing scenario, which facilitates taking corrective actions and implementing effective risk management. Perhaps most importantly, quantification of the uncertainties is an intrinsic part of the risk results. This approach to safety analysis has demonstrated many advantages of applying QRA principles to assessing the risk of facilities involving hazardous materials.

  4. [Microbiological Aspects of Radioactive Waste Storage].

    PubMed

    Safonov, A V; Gorbunova, O A; German, K E; Zakharova, E V; Tregubova, V E; Ershov, B G; Nazina, T N

    2015-01-01

    The article gives information about the microorganisms inhabiting in surface storages of solid radioactive waste and deep disposal sites of liquid radioactive waste. It was shown that intensification of microbial processes can lead to significant changes in the chemical composition and physical state of the radioactive waste. It was concluded that the biogeochemical processes can have both a positive effect on the safety of radioactive waste storages (immobilization of RW macrocomponents, a decreased migration ability of radionuclides) and a negative one (biogenic gas production in subterranean formations and destruction of cement matrix).

  5. Mission impossible? - Government Agencies And Public Relations For Nuclear Waste Disposal In Germany

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

    Landsmann, B.; Brauer, V.

    2007-07-01

    Analyzing the opinion of European Union citizens on the management of radioactive waste a survey of 2005 shows that European citizens are almost unanimous in the need to set up a national strategy for high-level radioactive waste disposal without any delay. While 45% of respondents consider that deep underground disposal represents the most appropriate solution for long-term management of highly radioactive waste, 38% disagree. In Germany, the divergence of opinion in this respect is very distinctive and it shows that, although experts believe that selected sites represent the best solution, this information does not yet seem to have reached themore » public. The reason therefore is both the lack of interesting and comprehensible information of issues related to nuclear waste disposal and negative media reporting always coupled with the negative public opinion about atomic energy in Germany. In Germany the siting, construction, and operation of a repository for radioactive waste is a national task. The Federal Institute for Geosciences and Natural Resources (BGR) as a government agency is a praxis oriented science institution and works on all geo-scientific and geotechnical issues in the German repository projects. According to its guidance BGR feels responsible for the future generations and is acting as a neutral and anticipatory partner for ministries and public authorities as well as a partner for industry, society and scientific bodies. BGR therefore is able to accomplish an essential contribution for the creation of public confidence for radioactive waste disposal due to precise public relations strategies. Sending the following messages is BGR's communication goal: - Radioactive waste can safely be disposed of in deep geological formations; - BGR is capable to handle this duty and delivers reliable results. Thereby, the BGR is in particular interested in passing on the information about nuclear waste disposal in a current and comprehensible way as well as providing arguments for the public. Public relations work of an authority should not only be to announce its expertise and consulting competence, but also to operate goal-orientated as a dialog partner and service provider of the community. BGR as an authority meets this challenge with the important advantage of accomplishing scientific research itself and thus delivering information first hand. In the last couple of years the BGR started to build its own public relations about its geo-scientific research. The BGR is planning to handle this dialog continuously, consistently and even strengthen it. Target groups are not only experts like research institutes and universities but also citizens as well as stakeholders and decision-makers. In order to fulfil the requirements of a comprehensive geo-scientific information policy, BGR is continuously enlarging its internet offer to the issue of nuclear waste disposal. The focal point concentrates on current, generally understandable words as well as on a wide offer about expert knowledge. Furthermore, the citizens shall be informed and sensitized about the topic of disposal by continuous media and press work. Through a target group oriented information in dialog with the public, state authorities, such as the BGR, are able to give an important contribution for the objectification of the 'disposal issue' and therefore more acceptance which could lead to more confidence within the population. BGR is analyzing international public relation concepts and is trying to transfer suitable strategies for public communication in Germany. Experience in Public Relations in the last four years have demonstrated that exciting as well as comprehensible information and an active presentation of topics of nuclear waste disposal consistently showed positive reactions and interest among the participants. (authors)« less

  6. 10 CFR 40.27 - General license for custody and long-term care of residual radioactive material disposal sites.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... disposed. In such cases, the Commission shall grant a license permitting use of the land if it finds that... the disposal site to be licensed, including documentation on whether land and interests are owned by the United States or an Indian tribe. If the site is on Indian land, then, as specified in the Uranium...

  7. Evaluation of Low-Level Waste Disposal Receipt Data for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2011

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

    French, Sean B.; Shuman, Robert

    2012-04-17

    The Los Alamos National Laboratory (LANL or the Laboratory) generates radioactive waste as a result of various activities. Operational or institutional waste is generated from a wide variety of research and development activities including nuclear weapons development, energy production, and medical research. Environmental restoration (ER), and decontamination and decommissioning (D and D) waste is generated as contaminated sites and facilities at LANL undergo cleanup or remediation. The majority of this waste is low-level radioactive waste (LLW) and is disposed of at the Technical Area 54 (TA-54), Area G disposal facility. U.S. Department of Energy (DOE) Order 435.1 (DOE, 2001) requiresmore » that radioactive waste be managed in a manner that protects public health and safety, and the environment. To comply with this order, DOE field sites must prepare and maintain site-specific radiological performance assessments for LLW disposal facilities that accept waste after September 26, 1988. Furthermore, sites are required to conduct composite analyses that account for the cumulative impacts of all waste that has been (or will be) disposed of at the facilities and other sources of radioactive material that may interact with the facilities. Revision 4 of the Area G performance assessment and composite analysis was issued in 2008 (LANL, 2008). These analyses estimate rates of radionuclide release from the waste disposed of at the facility, simulate the movement of radionuclides through the environment, and project potential radiation doses to humans for several on-site and off-site exposure scenarios. The assessments are based on existing site and disposal facility data and on assumptions about future rates and methods of waste disposal. The accuracy of the performance assessment and composite analysis depends upon the validity of the data used and assumptions made in conducting the analyses. If changes in these data and assumptions are significant, they may invalidate or call into question certain aspects of the analyses. For example, if the volumes and activities of waste disposed of during the remainder of the disposal facility's lifetime differ significantly from those projected, the doses projected by the analyses may no longer apply. DOE field sites are required to implement a performance assessment and composite analysis maintenance program. The purpose of this program is to ensure the continued applicability of the analyses through incremental improvement of the level of understanding of the disposal site and facility. Site personnel are required to conduct field and experimental work to reduce the uncertainty in the data and models used in the assessments. Furthermore, they are required to conduct periodic reviews of waste receipts, comparing them to projected waste disposal rates. The radiological inventory for Area G was updated in conjunction with Revision 4 of the performance assessment and composite analysis (Shuman, 2008). That effort used disposal records and other sources of information to estimate the quantities of radioactive waste that have been disposed of at Area G from 1959, the year the facility started receiving waste on a routine basis, through 2007. It also estimated the quantities of LLW that will require disposal from 2008 through 2044, the year in which it is assumed that disposal operations at Area G will cease. This report documents the fourth review of Area G disposal receipts since the inventory was updated and examines information for waste placed in the ground during fiscal years (FY) 2008 through 2011. The primary objective of the disposal receipt review is to ensure that the future waste inventory projections developed for the performance assessment and composite analysis are consistent with the actual types and quantities of waste being disposed of at Area G. Toward this end, the disposal data that are the subject of this review are used to update the future waste inventory projections for the disposal facility. These projections are compared to the future inventory projections that were developed for Revision 4 of the performance assessment and composite analysis. The approach used to characterize the FY 2008 through 2011 waste is generally the same as that used to characterize the inventory for the Revision 4 analyses (Shuman, 2008). This methodology is described in Section 2. The results of the disposal receipt review are presented in Section 3 and discussed in terms of their significance to the Area G analyses.« less

  8. Field Test to Evaluate Deep Borehole Disposal.

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

    Hardin, Ernest; Brady, Patrick Vane.; Clark, Andrew Jordan

    The U.S. Department of Energy (DOE) has embarked on the Deep Borehole Field Test (DBFT), which will investigate whether conditions suitable for disposal of radioactive waste can be found at a depth of up to 5 km in the earth’s crust. As planned, the DBFT will demonstrate drilling and construction of two boreholes, one for initial scientific characterization, and the other at a larger diameter such as could be appropriate for waste disposal (the DBFT will not involve radioactive waste). A wide range of geoscience activities is planned for the Characterization Borehole, and an engineering demonstration of test package emplacementmore » and retrieval is planned for the larger Field Test Borehole. Characterization activities will focus on measurements and samples that are important for evaluating the long-term isolation capability of the Deep Borehole Disposal (DBD) concept. Engineering demonstration activities will focus on providing data to evaluate the concept’s operational safety and practicality. Procurement of a scientifically acceptable DBFT site and a site management contractor is now underway. The concept of deep borehole disposal (DBD) for radioactive wastes is not new. It was considered by the National Academy of Science (NAS 1957) for liquid waste, studied in the 1980’s in the U.S. (Woodward–Clyde 1983), and has been evaluated by European waste disposal R&D programs in the past few decades (for example, Grundfelt and Crawford 2014; Grundfelt 2010). Deep injection of wastewater including hazardous wastes is ongoing in the U.S. and regulated by the Environmental Protection Agency (EPA 2001). The DBFT is being conducted with a view to use the DBD concept for future disposal of smaller-quantity, DOE-managed wastes from nuclear weapons production (i.e., Cs/Sr capsules and granular solid wastes). However, the concept may also have broader applicability for nations that have a need to dispose of limited amounts of spent fuel from nuclear power reactors. For such nations the cost for disposing of volumetrically limited waste streams could be lower than mined geologic repositories.« less

  9. Modeling Radionuclide Decay Chain Migration Using HYDROGEOCHEM

    NASA Astrophysics Data System (ADS)

    Lin, T. C.; Tsai, C. H.; Lai, K. H.; Chen, J. S.

    2014-12-01

    Nuclear technology has been employed for energy production for several decades. Although people receive many benefits from nuclear energy, there are inevitably environmental pollutions as well as human health threats posed by the radioactive materials releases from nuclear waste disposed in geological repositories or accidental releases of radionuclides from nuclear facilities. Theoretical studies have been undertaken to understand the transport of radionuclides in subsurface environments because that the radionuclide transport in groundwater is one of the main pathway in exposure scenarios for the intake of radionuclides. The radionuclide transport in groundwater can be predicted using analytical solution as well as numerical models. In this study, we simulate the transport of the radionuclide decay chain using HYDROGEOCHEM. The simulated results are verified against the analytical solution available in the literature. Excellent agreements between the numerical simulation and the analytical are observed for a wide spectrum of concentration. HYDROGECHEM is a useful tool assessing the ecological and environmental impact of the accidental radionuclide releases such as the Fukushima nuclear disaster where multiple radionuclides leaked through the reactor, subsequently contaminating the local groundwater and ocean seawater in the vicinity of the nuclear plant.

  10. Suitability of Palestine salt dome, Anderson Co. , Texas for disposal of high-level radioactive waste

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

    Patchick, P.F.

    1980-01-01

    The suitability of Palestine salt dome, in Anderson County, Texas, is in serious doubt for a repository to isolate high-level nuclear waste because of abandoned salt brining operations. The random geographic and spatial occurrence of 15 collapse sinks over the dome may prevent safe construction of the necessary surface installations for a repository. The dissolution of salt between the caprock and dome, from at least 15 brine wells up to 500 feet deep, may permit increased rates of salt dissolution long into future geologic time. The subsurface dissolution is occurring at a rate difficult, if not impossible, to assess ormore » to calculate. It cannot be shown that this dissolution rate is insignificant to the integrity of a future repository or to ancillary features. The most recent significant collapse was 36 feet in diameter and took place in 1972. The other collapses ranged from 27 to 105 feet in diameter and from 1.5 to more than 15 feet in depth. ONWI recommends that this dome be removed from consideration as a candidate site.« less

  11. Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel and Transuranic Radioactive Wastes (40 CFR Part 191)

    EPA Pesticide Factsheets

    This regulation sets environmental standards for public protection from the management and disposal of spent nuclear fuel, high-level wastes and wastes that contain elements with atomic numbers higher than uranium (transuranic wastes).

  12. 40 CFR 146.5 - Classification of injection wells.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ..., an underground source of drinking water. (2) Other industrial and municipal disposal wells which... underground source of drinking water. (3) Radioactive waste disposal wells which inject fluids below the lowermost formation containing an underground source of drinking water within one quarter mile of the well...

  13. 40 CFR 146.5 - Classification of injection wells.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ..., an underground source of drinking water. (2) Other industrial and municipal disposal wells which... underground source of drinking water. (3) Radioactive waste disposal wells which inject fluids below the lowermost formation containing an underground source of drinking water within one quarter mile of the well...

  14. 40 CFR 146.5 - Classification of injection wells.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ..., an underground source of drinking water. (2) Other industrial and municipal disposal wells which... underground source of drinking water. (3) Radioactive waste disposal wells which inject fluids below the lowermost formation containing an underground source of drinking water within one quarter mile of the well...

  15. 40 CFR 146.5 - Classification of injection wells.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ..., an underground source of drinking water. (2) Other industrial and municipal disposal wells which... underground source of drinking water. (3) Radioactive waste disposal wells which inject fluids below the lowermost formation containing an underground source of drinking water within one quarter mile of the well...

  16. 40 CFR 146.5 - Classification of injection wells.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ..., an underground source of drinking water. (2) Other industrial and municipal disposal wells which... underground source of drinking water. (3) Radioactive waste disposal wells which inject fluids below the lowermost formation containing an underground source of drinking water within one quarter mile of the well...

  17. 10 CFR 61.25 - Changes.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Changes. 61.25 Section 61.25 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.25 Changes... land disposal facility or procedures described in the license application. The license will include...

  18. 10 CFR 61.53 - Environmental monitoring.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.53 Environmental monitoring. (a) At the time a... radionuclides would indicate that the performance objectives of subpart C may not be met. (c) During the land...

  19. 10 CFR 61.42 - Protection of individuals from inadvertent intrusion.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ....42 Section 61.42 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.42 Protection of individuals from inadvertent intrusion. Design, operation, and closure of the land disposal facility must ensure protection of any...

  20. 10 CFR 61.55 - Waste classification.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Waste classification. 61.55 Section 61.55 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.55 Waste classification. (a) Classification of waste for near...

  1. 10 CFR 61.25 - Changes.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Changes. 61.25 Section 61.25 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.25 Changes... land disposal facility or procedures described in the license application. The license will include...

  2. 10 CFR 61.56 - Waste characteristics.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Waste characteristics. 61.56 Section 61.56 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.56 Waste characteristics. (a) The following requirements are...

  3. 10 CFR 61.25 - Changes.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Changes. 61.25 Section 61.25 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.25 Changes... land disposal facility or procedures described in the license application. The license will include...

  4. 10 CFR 61.55 - Waste classification.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Waste classification. 61.55 Section 61.55 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.55 Waste classification. (a) Classification of waste for near...

  5. 10 CFR 61.40 - General requirement.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false General requirement. 61.40 Section 61.40 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.40 General requirement. Land disposal facilities must be sited, designed, operated, closed...

  6. 10 CFR 61.56 - Waste characteristics.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Waste characteristics. 61.56 Section 61.56 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.56 Waste characteristics. (a) The following requirements are...

  7. 10 CFR 61.42 - Protection of individuals from inadvertent intrusion.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ....42 Section 61.42 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.42 Protection of individuals from inadvertent intrusion. Design, operation, and closure of the land disposal facility must ensure protection of any...

  8. 10 CFR 61.55 - Waste classification.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Waste classification. 61.55 Section 61.55 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.55 Waste classification. (a) Classification of waste for near...

  9. 10 CFR 61.56 - Waste characteristics.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Waste characteristics. 61.56 Section 61.56 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.56 Waste characteristics. (a) The following requirements are...

  10. 10 CFR 61.42 - Protection of individuals from inadvertent intrusion.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ....42 Section 61.42 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.42 Protection of individuals from inadvertent intrusion. Design, operation, and closure of the land disposal facility must ensure protection of any...

  11. 10 CFR 61.53 - Environmental monitoring.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.53 Environmental monitoring. (a) At the time a... radionuclides would indicate that the performance objectives of subpart C may not be met. (c) During the land...

  12. 10 CFR 61.56 - Waste characteristics.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Waste characteristics. 61.56 Section 61.56 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.56 Waste characteristics. (a) The following requirements are...

  13. 10 CFR 61.25 - Changes.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Changes. 61.25 Section 61.25 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.25 Changes... land disposal facility or procedures described in the license application. The license will include...

  14. 10 CFR 61.25 - Changes.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Changes. 61.25 Section 61.25 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.25 Changes... land disposal facility or procedures described in the license application. The license will include...

  15. 10 CFR 61.53 - Environmental monitoring.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.53 Environmental monitoring. (a) At the time a... radionuclides would indicate that the performance objectives of subpart C may not be met. (c) During the land...

  16. 10 CFR 61.56 - Waste characteristics.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Waste characteristics. 61.56 Section 61.56 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.56 Waste characteristics. (a) The following requirements are...

  17. 10 CFR 61.40 - General requirement.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false General requirement. 61.40 Section 61.40 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.40 General requirement. Land disposal facilities must be sited, designed, operated, closed...

  18. 77 FR 72997 - Low-Level Waste Disposal

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-07

    ...-2011-0012] RIN 3150-AI92 Low-Level Waste Disposal AGENCY: Nuclear Regulatory Commission. ACTION... Regulatory Commission (NRC) is proposing to amend its regulations that govern low-level radioactive waste... development of criteria for waste acceptance based on the results of these analyses. These amendments will...

  19. 10 CFR 61.40 - General requirement.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false General requirement. 61.40 Section 61.40 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.40 General requirement. Land disposal facilities must be sited, designed, operated, closed...

  20. 10 CFR 61.53 - Environmental monitoring.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.53 Environmental monitoring. (a) At the time a... radionuclides would indicate that the performance objectives of subpart C may not be met. (c) During the land...

  1. 10 CFR 61.42 - Protection of individuals from inadvertent intrusion.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ....42 Section 61.42 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.42 Protection of individuals from inadvertent intrusion. Design, operation, and closure of the land disposal facility must ensure protection of any...

  2. 10 CFR 61.42 - Protection of individuals from inadvertent intrusion.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ....42 Section 61.42 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.42 Protection of individuals from inadvertent intrusion. Design, operation, and closure of the land disposal facility must ensure protection of any...

  3. 10 CFR 61.40 - General requirement.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false General requirement. 61.40 Section 61.40 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.40 General requirement. Land disposal facilities must be sited, designed, operated, closed...

  4. 10 CFR 61.40 - General requirement.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false General requirement. 61.40 Section 61.40 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives § 61.40 General requirement. Land disposal facilities must be sited, designed, operated, closed...

  5. 10 CFR 61.53 - Environmental monitoring.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.53 Environmental monitoring. (a) At the time a... radionuclides would indicate that the performance objectives of subpart C may not be met. (c) During the land...

  6. Sanitary engineering aspects of nuclear energy developments*

    PubMed Central

    Kenny, A. W.

    1962-01-01

    So many developments have taken place in the field of nuclear energy since 1956, when the author's previous paper on radioactive waste disposal was published in the Bulletin of the World Health Organization, that a fresh review of the subject is now appropriate. The present paper deals with those aspects of the problem which are of most interest to the sanitary engineer. It considers specific points in the latest recommendations of the International Commission on Radiological Protection in relation to public drinking-water supplies, and examines the problem of fall-out, with special reference to the presence and significance of strontium-90 in drinking-water. A general survey of the various uses of radioactive materials is followed by a discussion of the legislative and control measures necessary to ensure safe disposal of wastes. The methods of waste disposal adopted in a number of nuclear energy establishments are described in detail. The paper concludes with some remarks on solid waste disposal, siting of nuclear energy industries and area monitoring. PMID:14455214

  7. Low-level radioactive waste management: transitioning to off-site disposal at Los Alamos National Laboratory

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

    Dorries, Alison M

    2010-11-09

    Facing the closure of nearly all on-site management and disposal capability for low-level radioactive waste (LLW), Los Alamos National Laboratory (LANL) is making ready to ship the majority of LLW off-site. In order to ship off-site, waste must meet the Treatment, Storage, and Disposal Facility's (TSDF) Waste Acceptance Criteria (WAC). In preparation, LANL's waste management organization must ensure LANL waste generators characterize and package waste compliantly and waste characterization documentation is complete and accurate. Key challenges that must be addressed to successfully make the shift to off-site disposal of LLW include improving the detail, accuracy, and quality of process knowledgemore » (PK) and acceptable knowledge (AK) documentation, training waste generators and waste management staff on the higher standard of data quality and expectations, improved WAC compliance for off-site facilities, and enhanced quality assurance throughout the process. Certification of LANL generators will allow direct off-site shipping of LLW from their facilities.« less

  8. Special Analysis: 2017-001 Disposal of Drums Containing Enriched Uranium in Pit 38 at Technical Area 54, Area G

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

    Birdsell, Kay Hanson; Stauffer, Philip H.; French, Sean B.

    Los Alamos National Laboratory (LANL) generates radioactive waste as a result of various activities. Operational waste is generated from a wide variety of research and development activities including nuclear weapons development, energy production, and medical research. Environmental restoration (ER), and decontamination and decommissioning (D&D) waste is generated as contaminated sites and facilities at LANL undergo cleanup or remediation. The majority of this waste is low-level radioactive waste (LLW) and is disposed of at the Technical Area 54 (TA-54), Area G disposal facility. This special analysis, SA 2017-001, evaluates the potential impacts of disposing of this waste in Pit 38 atmore » Area G based on the assumptions that form the basis of the Area G PA/CA. Section 2 describes the methods used to conduct the analysis; the results of the evaluation are provided in Section 3; and conclusions and recommendations are provided in Section 4.« less

  9. Beatty, Nevada: A section in U.S. Geological Survey research in radioactive waste disposal - Fiscal years 1983, 1984, and 1985 (WRI 87-4009)

    USGS Publications Warehouse

    Fischer, Jeffrey M.; Nichols, William D.; Dinwiddie, G.A.; Trask, N.J.

    1986-01-01

    A commercial low-level radioactive-waste disposal site has been operating near Beatty, Nevada, about 150 km northwest of Las Vegas, since 1962. The 32-ha site is situated in a desolate region of the Amargosa River Valley, sometimes referred to as the Amargosa Desert. Average annual precipitation is only about 114 mm. The site is underlain by 175 m of unconsolidated, generally coarse-grained, alluvial-fan and flood-plain deposits. The water table is at a depth of 90 m.

  10. Records of wells and chemical analyses of water from wells for the period June 13, 1984 to December 4, 1986 at the Maxey Flats Radioactive Waste Disposal Site, Kentucky

    USGS Publications Warehouse

    Lyverse, M.A.

    1987-01-01

    Lithologic data are presented for 113 wells drilled at the Maxey Flats Radioactive Waste Disposal Site for the period June 13, 1984 to December 4, 1986. Water levels, tritium concentrations, and specific conductance are also presented for wells yielding sufficient water for measuring and sampling. At least one sample was collected from most wells for the determination of gross alpha and beta activity. These activities and the results for gamma emitting radionuclides (Cobalt 60 and Cesium 137) are also presented. (USGS)

  11. Overview of ORNL/NRC programs addressing durability of concrete structures

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

    Naus, D.J.; Oland, C.B.

    1994-06-01

    The role of reinforced concrete relative to its applications as either safety-related structures in nuclear power or engineered barriers of low-level radioactive waste disposal facilities is described. Factors that can affect the long-term durability of reinforced concrete are identified. Overviews are presented of the Structural Aging Program, which is addressing the aging management of safety-related concrete structures in nuclear power plants, and the Permeability Test Methods and Data Program, which is identifying pertinent data and information for use in performance assessments of engineered barriers for low-level radioactive waste disposal.

  12. Geologic and hydrologic data collected during 1976-1983 at the Sheffield low-level radioactive waste disposal site and adjacent areas, Sheffield, Illinois

    USGS Publications Warehouse

    Foster, J.B.; Garklavs, George; Mackey, G.W.

    1984-01-01

    Hydrogeologic studies were conducted at the low-level radioactive-waste disposal site near Sheffield, Illinois, from 1976-84. Data in this report include water levels in wells, lake stages, inorganic, organic, and radiometric chemical analyses of ground and surface water, hydraulic conductivities of glacial materials, grain-size distribution, clay and carbonate mineralogy, and cation exchange capacities of the glacial materials. Also included are results of petrographic analyses, physical measurements of wells, stratigraphy and lithology of cores collected from test wells, and horizontal coordinates of wells.

  13. Special Analysis: 2016-001 Analysis of the Potential Under-Reporting of Am-241 Inventory for Nitrate Salt Waste at Area G

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

    Chu, Shaoping; Stauffer, Philip H.; Birdsell, Kay Hanson

    The Los Alamos National Laboratory (LANL) generates radioactive waste as a result of various activities. Operational waste is generated from a wide variety of research and development activities including nuclear weapons development, energy production, and medical research. Environmental restoration (ER), and decontamination and decommissioning (D&D) waste is generated as contaminated sites and facilities at LANL undergo cleanup or remediation. The majority of this waste is low-level radioactive waste (LLW) and is disposed of at the Technical Area 54 (TA-54), Area G disposal facility.

  14. Nuclear criticality safety assessment of the low level radioactive waste disposal facility trenches

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

    Kahook, S.D.

    1994-04-01

    Results of the analyses performed to evaluate the possibility of nuclear criticality in the Low Level Radioactive Waste Disposal Facility (LLRWDF) trenches are documented in this report. The studies presented in this document are limited to assessment of the possibility of criticality due to existing conditions in the LLRWDF. This document does not propose nor set limits for enriched uranium (EU) burial in the LLRWDF and is not a nuclear criticality safety evaluation nor analysis. The calculations presented in the report are Level 2 calculations as defined by the E7 Procedure 2.31, Engineering Calculations.

  15. 10 CFR 1.41 - Office of Federal and State Materials and Environmental Management Programs.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... to the States as provided by section 274i of the Act and also to NRC staff and staff of the U.S. Navy... radioactive isotopes; (21) Oversees safe management and disposal of low-level radioactive wastes; (22) Plans...

  16. 10 CFR 1.41 - Office of Federal and State Materials and Environmental Management Programs.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... to the States as provided by section 274i of the Act and also to NRC staff and staff of the U.S. Navy... radioactive isotopes; (21) Oversees safe management and disposal of low-level radioactive wastes; (22) Plans...

  17. 10 CFR 1.41 - Office of Federal and State Materials and Environmental Management Programs.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... to the States as provided by section 274i of the Act and also to NRC staff and staff of the U.S. Navy... radioactive isotopes; (21) Oversees safe management and disposal of low-level radioactive wastes; (22) Plans...

  18. 10 CFR 1.41 - Office of Federal and State Materials and Environmental Management Programs.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... to the States as provided by section 274i of the Act and also to NRC staff and staff of the U.S. Navy... radioactive isotopes; (21) Oversees safe management and disposal of low-level radioactive wastes; (22) Plans...

  19. 10 CFR 1.41 - Office of Federal and State Materials and Environmental Management Programs.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... to the States as provided by section 274i of the Act and also to NRC staff and staff of the U.S. Navy... radioactive isotopes; (21) Oversees safe management and disposal of low-level radioactive wastes; (22) Plans...

  20. On the possibility of galactic cosmic ray-induced radiolysis-powered life in subsurface environments in the Universe.

    PubMed

    Atri, Dimitra

    2016-10-01

    Photosynthesis is a mechanism developed by terrestrial life to utilize the energy from photons of solar origin for biological use. Subsurface regions are isolated from the photosphere, and consequently are incapable of utilizing this energy. This opens up the opportunity for life to evolve alternative mechanisms for harvesting available energy. Bacterium Candidatus Desulforudis audaxviator, found 2.8 km deep in a South African mine, harvests energy from radiolysis, induced by particles emitted from radioactive U, Th and K present in surrounding rock. Another radiation source in the subsurface environments is secondary particles generated by galactic cosmic rays (GCRs). Using Monte Carlo simulations, it is shown that it is a steady source of energy comparable to that produced by radioactive substances, and the possibility of a slow metabolizing life flourishing on it cannot be ruled out. Two mechanisms are proposed through which GCR-induced secondary particles can be utilized for biological use in subsurface environments: (i) GCRs injecting energy in the environment through particle-induced radiolysis and (ii) organic synthesis from GCR secondaries interacting with the medium. Laboratory experiments to test these hypotheses are also proposed. Implications of these mechanisms on finding life in the Solar System and elsewhere in the Universe are discussed. © 2016 The Author(s).

  1. On the possibility of galactic cosmic ray-induced radiolysis-powered life in subsurface environments in the Universe

    PubMed Central

    2016-01-01

    Photosynthesis is a mechanism developed by terrestrial life to utilize the energy from photons of solar origin for biological use. Subsurface regions are isolated from the photosphere, and consequently are incapable of utilizing this energy. This opens up the opportunity for life to evolve alternative mechanisms for harvesting available energy. Bacterium Candidatus Desulforudis audaxviator, found 2.8 km deep in a South African mine, harvests energy from radiolysis, induced by particles emitted from radioactive U, Th and K present in surrounding rock. Another radiation source in the subsurface environments is secondary particles generated by galactic cosmic rays (GCRs). Using Monte Carlo simulations, it is shown that it is a steady source of energy comparable to that produced by radioactive substances, and the possibility of a slow metabolizing life flourishing on it cannot be ruled out. Two mechanisms are proposed through which GCR-induced secondary particles can be utilized for biological use in subsurface environments: (i) GCRs injecting energy in the environment through particle-induced radiolysis and (ii) organic synthesis from GCR secondaries interacting with the medium. Laboratory experiments to test these hypotheses are also proposed. Implications of these mechanisms on finding life in the Solar System and elsewhere in the Universe are discussed. PMID:27707907

  2. Sandia National Laboratories support of the Iraq Nuclear Facility Dismantlement and Disposal Program.

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

    Cochran, John Russell; Danneels, Jeffrey John

    2009-03-01

    Because of past military operations, lack of upkeep and looting there are now enormous radioactive waste problems in Iraq. These waste problems include destroyed nuclear facilities, uncharacterized radioactive wastes, liquid radioactive waste in underground tanks, wastes related to the production of yellow cake, sealed radioactive sources, activated metals and contaminated metals that must be constantly guarded. Iraq currently lacks the trained personnel, regulatory and physical infrastructure to safely and securely manage these facilities and wastes. In 2005 the International Atomic Energy Agency (IAEA) agreed to organize an international cooperative program to assist Iraq with these issues. Soon after, the Iraqmore » Nuclear Facility Dismantlement and Disposal Program (the NDs Program) was initiated by the U.S. Department of State (DOS) to support the IAEA and assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials. The Iraq NDs Program is providing support for the IAEA plus training, consultation and limited equipment to the GOI. The GOI owns the problems and will be responsible for implementation of the Iraq NDs Program. Sandia National Laboratories (Sandia) is a part of the DOS's team implementing the Iraq NDs Program. This report documents Sandia's support of the Iraq NDs Program, which has developed into three principal work streams: (1) training and technical consultation; (2) introducing Iraqis to modern decommissioning and waste management practices; and (3) supporting the IAEA, as they assist the GOI. Examples of each of these work streams include: (1) presentation of a three-day training workshop on 'Practical Concepts for Safe Disposal of Low-Level Radioactive Waste in Arid Settings;' (2) leading GOI representatives on a tour of two operating low level radioactive waste disposal facilities in the U.S.; and (3) supporting the IAEA's Technical Meeting with the GOI from April 21-25, 2008. As noted in the report, there was significant teaming between the various participants to best help the GOI. On-the-ground progress is the focus of the Iraq NDs Program and much of the work is a transfer of technical and practical skills and knowledge that Sandia uses day-to-day. On-the-ground progress was achieved in July of 2008 when the GOI began the physical cleanup and dismantlement of the Active Metallurgical Testing Laboratory (LAMA) facility at Al Tuwaitha, near Baghdad.« less

  3. How to recycle asbestos containing materials (ACM)

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

    Jantzen, C.M.

    The current disposal of asbestos containing materials (ACM) in the private sector consists of sealing asbestos wetted with water in plastic for safe transportation and burial in regulated land fills. This disposal methodology requires large disposal volumes especially for asbestos covered pipe and asbestos/fiberglass adhering to metal framework, e.g. filters. This wrap and bury technology precludes recycle of the asbestos, the pipe and/or the metal frameworks. Safe disposal of ACM at U.S. Department of Energy (DOE) sites, likewise, requires large disposal volumes in landfills for non-radioactive ACM and large disposal volumes in radioactive burial grounds for radioactive and suspect contaminatedmore » ACM. The availability of regulated disposal sites is rapidly diminishing causing recycle to be a more attractive option. Asbestos adhering to metal (e.g., pipes) can be recycled by safely removing the asbestos from the metal in a patented hot caustic bath which prevents airborne contamination /inhalation of asbestos fibers. The dissolution residue (caustic and asbestos) can be wet slurry fed to a melter and vitrified into a glass or glass-ceramic. Palex glasses, which are commercially manufactured, are shown to be preferred over conventional borosilicate glasses. The Palex glasses are alkali magnesium silicate glasses derived by substituting MgO for B{sub 2}O{sub 3} in borosilicate type glasses. Palex glasses are very tolerant of the high MgO and high CaO content of the fillers used in forming asbestos coverings for pipes and found in boiler lashing, e.g., hydromagnesite (3MgCO{sub 3} Mg(OH){sub 2} 3H{sub 2}O) and plaster of paris, gypsum (CaSO{sub 4}). The high temperate of the vitrification process destroys the asbestos fibers and renders the asbestos non-hazardous, e.g., a glass or glass-ceramic. In this manner the glass or glass-ceramic produced can be recycled, e.g., glassphalt or glasscrete, as can the clean metal pipe or metal framework.« less

  4. Environmental Assessment for Selection and Operation of the Proposed Field Research Centers for the Natural and Accelerated Bioremediation Research (NABIR) Program

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

    N /A

    2000-04-18

    The US Department of Energy (DOE) Office of Biological and Environmental Research (OBER), within the Office of Science (SC), proposes to add a Field Research Center (FRC) component to the existing Natural and Accelerated Bioremediation Research (NABIR) Program. The NABIR Program is a ten-year fundamental research program designed to increase the understanding of fundamental biogeochemical processes that would allow the use of bioremediation approaches for cleaning up DOE's contaminated legacy waste sites. An FRC would be integrated with the existing and future laboratory and field research and would provide a means of examining the fundamental biogeochemical processes that influence bioremediationmore » under controlled small-scale field conditions. The NABIR Program would continue to perform fundamental research that might lead to promising bioremediation technologies that could be demonstrated by other means in the future. For over 50 years, DOE and its predecessor agencies have been responsible for the research, design, and production of nuclear weapons, as well as other energy-related research and development efforts. DOE's weapons production and research activities generated hazardous, mixed, and radioactive waste products. Past disposal practices have led to the contamination of soils, sediments, and groundwater with complex and exotic mixtures of compounds. This contamination and its associated costs and risks represents a major concern to DOE and the public. The high costs, long duration, and technical challenges associated with remediating the subsurface contamination at DOE sites present a significant need for fundamental research in the biological, chemical, and physical sciences that will contribute to new and cost-effective solutions. One possible low-cost approach for remediating the subsurface contamination of DOE sites is through the use of a technology known as bioremediation. Bioremediation has been defined as the use of microorganisms to biodegrade or biotransform hazardous organic contaminants to environmentally safe levels in soils, subsurface materials, water, sludges, and residues.. While bioremediation technology is promising, DOE managers and non-DOE scientists have recognized that the fundamental scientific information needed to develop effective bioremediation technologies for cleanup of the legacy waste sites is lacking in many cases. DOE believes that field-based research is needed to realize the full potential of bioremediation. The Department of Energy faces a unique set of challenges associated with cleaning up waste at its former weapons production and research sites. These sites contain complex mixtures of contaminants in the subsurface, including radioactive compounds. In many cases, the fundamental field-based scientific information needed to develop safe and effective remediation and cleanup technologies is lacking. DOE needs fundamental research on the use of microorganisms and their products to assist DOE in the decontamination and cleanup of its legacy waste sites. The existing NABIR program to-date has focused on fundamental scientific research in the laboratory. Because subsurface hydrologic and geologic conditions at contaminated DOE sites cannot easily be duplicated in a laboratory, however, the DOE needs a field component to permit existing and future laboratory research results to be field-tested on a small scale in a controlled outdoor setting. Such field-testing needs to be conducted under actual legacy waste field conditions representative of those that DOE is most in need of remediating. Ideally, these field conditions should be as representative as practicable of the types of subsurface contamination conditions that resulted from legacy wastes from the nuclear weapons program activities. They should also be representative of the types of hydrologic and geologic conditions that exist across the DOE complex.« less

  5. Advances in Multiphase Flow and Transport in the Subsurface Environment

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

    Shi, Xiaoqing; Finsterle, Stefan; Zhang, Keni

    Multiphase flow and transport processes in the subsurface environment are extremely important in a number of industrial and environmental applications at various spatial and temporal scales. Thus, it is necessary to identify, understand, and predict these processes to improve the production of conventional and unconventional oil and gas, to increase the safety of geological sequestration of carbon dioxide and nuclear waste disposal, and to make remediation of contaminated aquifers more effective.

  6. Advances in Multiphase Flow and Transport in the Subsurface Environment

    DOE PAGES

    Shi, Xiaoqing; Finsterle, Stefan; Zhang, Keni; ...

    2018-03-04

    Multiphase flow and transport processes in the subsurface environment are extremely important in a number of industrial and environmental applications at various spatial and temporal scales. Thus, it is necessary to identify, understand, and predict these processes to improve the production of conventional and unconventional oil and gas, to increase the safety of geological sequestration of carbon dioxide and nuclear waste disposal, and to make remediation of contaminated aquifers more effective.

  7. 10 CFR 63.302 - Definitions for Subpart L.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Definitions for Subpart L. 63.302 Section 63.302 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN A GEOLOGIC... hydraulic conductivity, gradient, and the screened interval. Yucca Mountain disposal system means the...

  8. 10 CFR 63.302 - Definitions for Subpart L.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Definitions for Subpart L. 63.302 Section 63.302 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN A GEOLOGIC... hydraulic conductivity, gradient, and the screened interval. Yucca Mountain disposal system means the...

  9. 10 CFR 63.302 - Definitions for Subpart L.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Definitions for Subpart L. 63.302 Section 63.302 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN A GEOLOGIC... hydraulic conductivity, gradient, and the screened interval. Yucca Mountain disposal system means the...

  10. 40 CFR 191.11 - Applicability.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... required to be characterized under section 113(a) of Public Law 97-425, 96 Stat. 2201. [50 FR 38084, Sept... ENVIRONMENTAL RADIATION PROTECTION STANDARDS FOR MANAGEMENT AND DISPOSAL OF SPENT NUCLEAR FUEL, HIGH-LEVEL AND TRANSURANIC RADIOACTIVE WASTES Environmental Standards for Disposal § 191.11 Applicability. (a) This subpart...

  11. 10 CFR 61.14 - Institutional information.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Institutional information. 61.14 Section 61.14 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE... proposed disposal site is on land not owned by the Federal or a State government, the applicant must submit...

  12. 10 CFR 61.57 - Labeling.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.57 Labeling. Each package of waste must be clearly labeled to identify whether it is Class A waste, Class B waste, or Class C waste, in accordance with § 61.55. ...

  13. 10 CFR 61.58 - Alternative requirements for waste classification and characteristics.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.58 Alternative requirements for waste classification and characteristics. The Commission may, upon request or on... 10 Energy 2 2014-01-01 2014-01-01 false Alternative requirements for waste classification and...

  14. 10 CFR 61.57 - Labeling.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.57 Labeling. Each package of waste must be clearly labeled to identify whether it is Class A waste, Class B waste, or Class C waste, in accordance with § 61.55. ...

  15. 10 CFR 61.14 - Institutional information.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Institutional information. 61.14 Section 61.14 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE... proposed disposal site is on land not owned by the Federal or a State government, the applicant must submit...

  16. 10 CFR 61.57 - Labeling.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.57 Labeling. Each package of waste must be clearly labeled to identify whether it is Class A waste, Class B waste, or Class C waste, in accordance with § 61.55. ...

  17. 10 CFR 61.14 - Institutional information.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Institutional information. 61.14 Section 61.14 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE... proposed disposal site is on land not owned by the Federal or a State government, the applicant must submit...

  18. 10 CFR 61.57 - Labeling.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.57 Labeling. Each package of waste must be clearly labeled to identify whether it is Class A waste, Class B waste, or Class C waste, in accordance with § 61.55. ...

  19. 10 CFR 61.58 - Alternative requirements for waste classification and characteristics.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.58 Alternative requirements for waste classification and characteristics. The Commission may, upon request or on... 10 Energy 2 2012-01-01 2012-01-01 false Alternative requirements for waste classification and...

  20. 10 CFR 61.58 - Alternative requirements for waste classification and characteristics.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.58 Alternative requirements for waste classification and characteristics. The Commission may, upon request or on... 10 Energy 2 2010-01-01 2010-01-01 false Alternative requirements for waste classification and...

  1. 10 CFR 61.23 - Standards for issuance of a license.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.23 Standards for issuance of a license. A license for the receipt, possession, and disposal of waste containing or contaminated with source, special nuclear, or byproduct material will be...

  2. 10 CFR 61.58 - Alternative requirements for waste classification and characteristics.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.58 Alternative requirements for waste classification and characteristics. The Commission may, upon request or on... 10 Energy 2 2013-01-01 2013-01-01 false Alternative requirements for waste classification and...

  3. 10 CFR 61.14 - Institutional information.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Institutional information. 61.14 Section 61.14 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE... proposed disposal site is on land not owned by the Federal or a State government, the applicant must submit...

  4. 10 CFR 61.23 - Standards for issuance of a license.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.23 Standards for issuance of a license. A license for the receipt, possession, and disposal of waste containing or contaminated with source, special nuclear, or byproduct material will be...

  5. 10 CFR 61.23 - Standards for issuance of a license.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.23 Standards for issuance of a license. A license for the receipt, possession, and disposal of waste containing or contaminated with source, special nuclear, or byproduct material will be...

  6. 10 CFR 61.23 - Standards for issuance of a license.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.23 Standards for issuance of a license. A license for the receipt, possession, and disposal of waste containing or contaminated with source, special nuclear, or byproduct material will be...

  7. 10 CFR 61.23 - Standards for issuance of a license.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Licenses § 61.23 Standards for issuance of a license. A license for the receipt, possession, and disposal of waste containing or contaminated with source, special nuclear, or byproduct material will be...

  8. 10 CFR 61.57 - Labeling.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.57 Labeling. Each package of waste must be clearly labeled to identify whether it is Class A waste, Class B waste, or Class C waste, in accordance with § 61.55. ...

  9. 10 CFR 61.14 - Institutional information.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Institutional information. 61.14 Section 61.14 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE... proposed disposal site is on land not owned by the Federal or a State government, the applicant must submit...

  10. 10 CFR 61.58 - Alternative requirements for waste classification and characteristics.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.58 Alternative requirements for waste classification and characteristics. The Commission may, upon request or on... 10 Energy 2 2011-01-01 2011-01-01 false Alternative requirements for waste classification and...

  11. Beatty, Nevada: A section in U.S. Geological Survey research in radioactive waste disposal - Fiscal years 1986-1990 (WRI 91-4084)

    USGS Publications Warehouse

    Andraski, Brian J.; Fisher, Jeffrey M.; Prudic, David E.; Trask, N.J.; Stevens, P.R.

    1991-01-01

    A low-level radioactive-waste disposal facility in the Amargosa Desert of Nevada, about 17 km southeast of Beatty and 169 km northwest of Las Vegas, has been operating since 1962. This was the first commercially operated radioactive waste disposal facility in the United States. Wastes at the facility are emplaced in 2 to 15-m deep trenches and covered by backfilling with previously excavated materials. Annual precipitation in the area averages about 112 mm. Vegetation is sparse with creosote bush (Larrea tridentata) being the dominant species. Soils in the area are skeletal and are underlain by more than 170 m of unconsolidated alluvial-fan, fluvial, and ephemeral-lake deposits. Depth to water is about 85 m.Initial field investigations (1976-1980) included monitoring of soil-water content and water potential in an unvegetated soil profile, and collection of meteorological data at the disposal facility. Design of additional hydrogeologic investigations and long-term studies of soil-water movement in a vegetated soil profile began in 1982 and field data collection has been ongoing since 1984. Studies to evaluate the modifying effects of trench construction on the natural site environment and to determine changes in trench structural stability began in 1987. Design of studies to measure gas and vapor movement in the trenches at the facility began in 1989.

  12. Method of measuring a profile of the density of charged particles in a particle beam

    DOEpatents

    Hyman, L.G.; Jankowski, D.J.

    1975-10-01

    A profile of the relative density of charged particles in a beam is obtained by disposing a number of rods parallel to each other in a plane perpendicular to the beam and shadowing the beam. A second number of rods is disposed perpendicular to the first rods in a plane perpendicular to the beam and also shadowing the beam. Irradiation of the rods by the beam of charged particles creates radioactive isotopes in a quantity proportional to the number of charged particles incident upon the rods. Measurement of the radioactivity of each of the rods provides a measure of the quantity of radioactive material generated thereby and, together with the location of the rods, provides information sufficient to identify a profile of the density of charged particles in the beam.

  13. Disposal of Radioactive Waste at Hanford Creates Problems

    ERIC Educational Resources Information Center

    Chemical and Engineering News, 1978

    1978-01-01

    Radioactive storage tanks at the Hanford facility have developed leaks. The situation is presently considered safe, but serious. A report from the National Academy of Science has recommended that the wastes be converted to stable solids and stored at another site on the Hanford Reservation. (Author/MA)

  14. 10 CFR 61.80 - Maintenance of records, reports, and transfers.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... receipt and disposal of radioactive waste in an electronic recordkeeping system. (1) The manifest... RADIOACTIVE WASTE Records, Reports, Tests, and Inspections § 61.80 Maintenance of records, reports, and.... The record may also be stored in electronic media with the capability for producing legible, accurate...

  15. Storage of nuclear materials by encapsulation in fullerenes

    DOEpatents

    Coppa, Nicholas V.

    1994-01-01

    A method of encapsulating radioactive materials inside fullerenes for stable long-term storage. Fullerenes provide a safe and efficient means of disposing of nuclear waste which is extremely stable with respect to the environment. After encapsulation, a radioactive ion is essentially chemically isolated from its external environment.

  16. 10 CFR 61.80 - Maintenance of records, reports, and transfers.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... Section 61.80 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Records, Reports, Tests, and Inspections § 61.80 Maintenance of records, reports, and..., the licensee shall record the location and the quantity of radioactive wastes contained in the...

  17. 10 CFR 61.80 - Maintenance of records, reports, and transfers.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... Section 61.80 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Records, Reports, Tests, and Inspections § 61.80 Maintenance of records, reports, and..., the licensee shall record the location and the quantity of radioactive wastes contained in the...

  18. 10 CFR 61.80 - Maintenance of records, reports, and transfers.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... Section 61.80 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Records, Reports, Tests, and Inspections § 61.80 Maintenance of records, reports, and..., the licensee shall record the location and the quantity of radioactive wastes contained in the...

  19. SUBGRADE MONOLITHIC ENCASEMENT STABILIZATION OF CATEGORY 3 LOW LEVEL WASTE (LLW)

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

    PHILLIPS, S.J.

    2004-02-03

    A highly efficient and effective technology has been developed and is being used for stabilization of Hazard Category 3 low-level waste at the U.S. Department of Energy's Hanford Site. Using large, structurally interconnected monoliths, which form one large monolith that fills a waste disposal trench, the patented technology can be used for final internment of almost any hazardous, radioactive, or toxic waste or combinations of these waste materials packaged in a variety of sizes, shapes, and volumes within governmental regulatory limits. The technology increases waste volumetric loading by 100 percent, area use efficiency by 200 percent, and volumetric configuration efficiencymore » by more than 500 percent over past practices. To date, in excess of 2,010 m{sup 3} of contact-handled and remote-handled low-level radioactive waste have been interned using this patented technology. Additionally, in excess of 120 m{sup 3} of low-level radioactive waste requiring stabilization in low-diffusion coefficient waste encasement matrix has been disposed using this technology. Greater than five orders of magnitude in radiation exposure reduction have been noted using this method of encasement of Hazard Category 3 waste. Additionally, exposure monitored at all monolith locations produced by the slip form technology is less than 1.29 x E-07 C {center_dot} kg{sup -1}. Monolithic encasement of Hazard Category 3 low-level waste and other waste category materials may be successfully accomplished using this technology at nominally any governmental or private sector waste disposal facility. Additionally, other waste materials consisting of hazardous, radioactive, toxic, or mixed waste materials can be disposed of using the monolithic slip form encasement technology.« less

  20. Site Environmental Report for Calendar Year 2007. DOE Operations at The Boeing Company, Santa Susana Field Laboratory, Area IV

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

    Liu, Ning; Rutherford, Phil; Lenox, Art

    2008-09-30

    This Annual Site Environmental Report (ASER) for 2007 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). The Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder components. All nuclear work was terminated in 1988; all subsequentmore » radiological work has been directed toward decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. In May 2007, the D&D operations in Area IV were suspended until DOE completes the SSFL Area IV Environmental Impact Statement (EIS). The environmental monitoring programs were continued throughout the year. Results of the radiological monitoring program for the calendar year 2007 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling. All radioactive wastes are processed for disposal at DOE disposal sites and/or other licensed sites approved by DOE for radioactive waste disposal. No liquid radioactive wastes were released into the environment in 2007.« less

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