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Sample records for laboratory gunite tank

  1. Technology study of Gunite tank sludge mobilization at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    DeVore, J.R.; Herrick, T.J.; Lott, K.E.

    1994-12-01

    The Oak Ridge National Laboratory (ORNL) Gunite Tank Sludge Mobilization Technology Study was initiated to support the Gunite Tank Treatability Study effort. The technology study surveyed the methods and technologies available for tank cleaning and sludge mobilization in a radioactive environment. Technologies were identified and considered for applicability to the Gunite and Associated Tanks (GAAT) problems. These were then either accepted for further study or rejected as not applicable. Technologies deemed applicable to the GAAT sludge removal project were grouped for evaluation according to (1) deployment method, (2) types of remotely operated end effector equipment applicable to removal of sludge, (3) methods for removing wastes from the tanks, and (4) methods for concrete removal. There were three major groups of deployment technologies: ``past practice`` technologies, mechanical arm-based technologies, and vehicle-based technologies. The different technologies were then combined into logical sequences of deployment platform, problem, end effector, conveyance, post-removal treatment required (if any), and disposition of the waste. Many waste removal options are available, but the best technology in one set of circumstances at one site might not be the best type to use at a different site. No single technology is capable of treating the entire spectrum of wastes that will be encountered in GAAT. None of the systems used in other industries appears to be suitable, primarily because of the nature of the sludges in the GAAT Operable Unit (OU), their radiation levels, and tank geometries. Other commercial technologies were investigated but rejected because the authors did not believe them to be applicable.

  2. Robotic system for decommissioning the Gunite tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Chesser, J.B.; Evans, J.H.; Norman, R.E.; Peishel, F.L.; Ruppel, F.R.

    1992-12-31

    Robotic systems and equipment to facilitate removal of the contents of the Oak Ridge National Laboratory (ORNL) Gunite Waste Tanks as well as the tanks themselves are one of several options being considered for this site. The technology described consists of proven remote systems and equipment or remote adaptations of proven industrial concepts. The proposed robotic system would be housed in a portable containment structure, fabricated from steel plate, and reinforced with structural shapes. The structure would be cylindrical and have a domed head. The containment structure would be sized to cover one tank. The tanks are in two sizes: 60 ft and 35 ft diameters. The structures would be supported on driven steel piles and would have an earthen berm around the base to enhance the effectiveness of the containment. Internal to the containment structure, a polar crane bridge equipped with a pair of trolley-mounted telescoping masts would be utilized to support and manipulate the systems, tools, etc., which would perform the individual tasks. The bridge and mast control system and the manipulator control system would provide both teleoperated and robotic modes to support either manual or preprogrammed operations. Equipment mounted at the end of the mast would include servomanipulators, water jet cutter, or a clam shell bucket. The mast would feature an interface plate allowing remote changeout of most mounted equipment. The operating system would be required to have the capability to decontaminate the dome and its equipment to the degree necessary to allow it to be relocated. Viewing would be provided by commercial closed-circuit TV (CCTV). It is believed that the systems described herein represent a feasible approach to removing the contents from the ORNL gunite tanks and implementing remediation of the site.

  3. Robotic system for decommissioning the Gunite tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Chesser, J.B.; Evans, J.H.; Norman, R.E.; Peishel, F.L.; Ruppel, F.R.

    1992-01-01

    Robotic systems and equipment to facilitate removal of the contents of the Oak Ridge National Laboratory (ORNL) Gunite Waste Tanks as well as the tanks themselves are one of several options being considered for this site. The technology described consists of proven remote systems and equipment or remote adaptations of proven industrial concepts. The proposed robotic system would be housed in a portable containment structure, fabricated from steel plate, and reinforced with structural shapes. The structure would be cylindrical and have a domed head. The containment structure would be sized to cover one tank. The tanks are in two sizes: 60 ft and 35 ft diameters. The structures would be supported on driven steel piles and would have an earthen berm around the base to enhance the effectiveness of the containment. Internal to the containment structure, a polar crane bridge equipped with a pair of trolley-mounted telescoping masts would be utilized to support and manipulate the systems, tools, etc., which would perform the individual tasks. The bridge and mast control system and the manipulator control system would provide both teleoperated and robotic modes to support either manual or preprogrammed operations. Equipment mounted at the end of the mast would include servomanipulators, water jet cutter, or a clam shell bucket. The mast would feature an interface plate allowing remote changeout of most mounted equipment. The operating system would be required to have the capability to decontaminate the dome and its equipment to the degree necessary to allow it to be relocated. Viewing would be provided by commercial closed-circuit TV (CCTV). It is believed that the systems described herein represent a feasible approach to removing the contents from the ORNL gunite tanks and implementing remediation of the site.

  4. Remote systems for waste retrieval from the Oak Ridge National Laboratory gunite tanks

    SciTech Connect

    Falter, D.D.; Babcock, S.M.; Burks, B.L.; Lloyd, P.D.; Randolph, J.D.; Rutenber, J.E.; Van Hoesen, S.D.

    1995-12-31

    As part of a Comprehensive Environmental Response, Compensation, and Liability Act Treatability Study funded by the Department of Energy, the Oak Ridge National Laboratory (ORNL) is preparing to demonstrate and evaluate two approaches for the remote retrieval of wastes in underground storage tanks. This work is being performed to identify the most cost-effective and efficient method of waste removal before full-scale remediation efforts begin in 1998. System requirements are based on the need to dislodge and remove sludge wastes ranging in consistency from broth to compacted clay from Gunite (Shotcrete) tanks that are approaching fifty years in age. Systems to be deployed must enter and exit through the existing 0.6 m (23.5 in.) risers and conduct retrieval operations without damaging the layered concrete walls of the tanks. Goals of this project include evaluation of confined sluicing techniques and successful demonstration of a telerobotic arm-based system for deployment of the sluicing system. As part of a sister project formed on the Old Hydrofracture Facility tanks at ORNL, vehicle-based tank remediation will also be evaluated.

  5. Results of 1995 characterization of Gunite and Associated Tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1996-02-01

    This technical memorandum (TM) documents the 1995 characterization of eight underground radioactive waste tanks at Oak Ridge National Laboratory (ORNL). These tanks belong to the Gunite and Associated Tanks (GAAT) operable unit, and the characterization is part of the ongoing GAAT remedial investigation/feasibility study (RI/FS) process. This TM reports both field observations and analytical results; analytical results are also available from the Oak Ridge Environmental Information System (OREIS) data base under the project name GAAT (PROJ-NAME = GAAT). This characterization effort (Phase II) was a follow-up to the {open_quotes}Phase I{close_quotes} sampling campaign reported in Results of Fall 1994 Sampling of Gunite and Associated Tanks at the Oak Ridge National Laboratory, Oak Ridge, Tennessee, ORNL/ER/Sub/87-99053/74, June 1995. The information contained here should be used in conjunction with that in the previous TM. The sampling plan is documented in ORNL Inactive Waste Tanks Sampling and Analysis Plan, ORNL/RAP/LTR-88/24, dated April 1988, as amended by Addendum 1, Revision 2: ORNL Inactive Tanks Sampling and Analysis Plan, DOE/OR/02-1354&D2, dated February 1995. Field team instructions are found in ORNL RI/FS Project Field Work Guides 01-WG-20, Field Work Guide for Sampling of Gunite and Associated Tanks, and 01-WG-21, Field Work Guide for Tank Characterization System Operations at ORNL. The field effort was conducted under the programmatic and procedural umbrella of the ORNL RI/FS Program, and the analysis was in accordance with ORNL Chemical and Analytical Sciences Division (CASD) procedures. The characterization campaign is intended to provide data for criticality safety, engineering design, and waste management as they apply to the GAAT treatability study and remediation. The Department of Energy (DOE) Carlsbad office was interested in results of this sampling campaign and provided funding for certain additional sample collection and analysis.

  6. Data management implementation plan for interim action at the Gunite and Associated Tanks, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1998-03-01

    The Gunite and Associated Tanks (GAAT) Project is currently conducting a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Interim Remedial Action to reduce uncertainties on the potential cost and effectiveness of remote tank cleaning equipment being produced jointly between the US Department of Energy (DOE); Oak Ridge National Laboratory (ORNL); Lockheed Martin Energy Systems, Inc.; and associated subcontractors with the DOE EM-50 Program. The goal of this document is to ensure that all procedures have been followed to provide reliable, verifiable data that are technically defensible. The data collected will be used to support closure of the tanks, compare the expected versus actual waste volume and curies to aid in conducting operations, and verify the performance of developmental equipment.

  7. North Tank Farm data report for the Gunite and Associated Tanks at Oak Ridge National Laboratory

    SciTech Connect

    Rule, V.A.; Burks, B.L.; Hoesen, S.D. van

    1998-05-01

    The US Department of Energy (DOE) Office of Science and Technology, in cooperation with the Oak Ridge Environmental Management Program, has developed and demonstrated the first full-scale remotely operated system for cleaning radioactive liquid and waste from large underground storage tanks. The remotely operated waste retrieval system developed and demonstrated at Oak Ridge National Laboratory (ORNL) is designed to accomplish both retrieval of bulk waste, including liquids, thick sludge, and scarified concrete, and final tank cleaning. This report provides a summary of the North Tank Farm (NTF) operations data and an assessment of the performance and efficiency of the waste retrieval system during NTF operations data and an assessment of the performance and efficiency of the waste retrieval system during NTF operations. The organization of this report is as follows: Section 1 provides an introduction to the report. Section 2 describes the NTF tank structures (W-3 and W-4 only) and the contents of the tanks. Section 3 outlines the objectives of the NTF testing and explains how these objectives were met. Section 4 provides a description of the various operating systems used in the NTF operations. Sections 5 and 6 present a summary of the data collected during NTF operations. Section 7 summarizes the maintenance activities performed and Section 8 summarizes the on-the-job training performed in the NTF. Section 9 summarizes the capital cost for the waste retrieval and characterization equipment and operating costs for performing the NTF work. Section 10 provides observations and lessons learned, and Section 11 provides a summary and conclusions.

  8. The Gunite Tanks Remediation Project at Oak Ridge National Laboratory; Successful Integration & Deployment of Technologies Results in Remediated Underground Storage Tanks

    SciTech Connect

    Billingsley, K.; Bolling, D.

    2002-02-27

    This paper presents an overview of the underground technologies deployed during the cleanup of nine large underground storage tanks (USTs) that contained residual radioactive sludge, liquid low-level waste (LLLW), and other debris. The Gunite Tanks Remediation Project at Oak Ridge National Laboratory (ORNL) was successfully completed in 2001, ending with the stabilization of the USTs and the cleanup of the South Tank Farm. This U.S. Department of Energy (DOE) project was the first of its kind completed in the United States of America. The Project integrated robotic and remotely operated technologies into an effective tank waste retrieval system that safely retrieved more than 348 m3 (92,000 gal) of radioactive sludge and 3.15E+15 Bq (85,000 Ci) of radioactive contamination from the tanks. The Project successfully transferred over 2,385 m3 (630,000 gal) of waste slurry to ORNL's active tank waste management system. The project team avoided over $120 Million in costs and shortened the original baseline schedule by over 10 years. Completing the Gunite Tanks Remediation Project eliminated the risks posed by the aging USTs and the waste they contained, and avoid the $400,000 annual costs associated with maintaining and monitoring the tanks.

  9. Evaluation and monitoring plan for consolidation tanks: Gunite and Associated Tanks Operable Unit, Waste Area Grouping 1, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1997-02-01

    This report describes the results of an integrity evaluation of Tanks W-8 and W-9, part of the Gunite and Associated Tanks (GAAT), in the South Tank Farm at Oak Ridge National Laboratory (ORNL), together with a plan for monitoring those tanks for potential releases during the GAAT CERCLA treatability study and waste removal activities. This work was done in support of an ORNL plan to use W-8 and W-9 as consolidation tanks during remediation of the other tanks in the North and South Tank Farms. The analysis portion of the report draws upon both tank-internal measurements of liquid volume change and tank-external measurements of the change in electrical conductivity of the groundwater in the dry wells adjacent to each tank. The results of the analysis show that both W-8 and W-9 are liquid-tight and are suitable for use as consolidation tanks. The recommended monitoring plan will utilize the dry well conductivity monitoring method as the primary release detection tool during the CERCLA activities. This method is expected to be able to detect releases of less than 0.5 gal/h with a 95% probability of detection, most of the time. The results described here validate three prior independent efforts: a liquid integrity assessment made in 1995, a structural integrity assessment made in 1995 by experts in the field of gunite tanks, and a structural integrity assessment made in 1994 using a three-dimensional, finite-element computer model. This work, along with the three prior efforts, shows that Tanks W-8 and W-9 are structurally sound and liquid-tight. Based upon this work it is concluded that these tanks are suitable for use as consolidation tanks during the GAAT CERCLA treatability study and waste removal actions and it is recommended that the tanks be monitored for potential releases during this period using the methods described in this report.

  10. Oak Ridge National Laboratory Gunite and Associated Tanks Stabilization Project-Low-Tech Approach with High-Tech Results

    SciTech Connect

    Brill, A.; Alsup, T.; Bolling, D.

    2002-02-26

    Environmental restoration of the Gunite and Associated Tanks (GAAT) at the Oak Ridge National Laboratory (ORNL) was a priority to the U. S. Department of Energy (DOE) because of their age and deteriorating structure. These eight tanks ranging up to 170,000 gallons in capacity were constructed in 1943 of a Gunite or ''sprayed concrete material'' as part of the Manhattan Project. The tanks initially received highly radioactive waste from the Graphite Reactor and associated chemical processing facilities. The waste was temporarily stored in these tanks to allow for radioactive decay prior to dilution and release into surface waters. Over time, additional wastes from ongoing ORNL operations (e.g., isotope separation and materials research) were discharged to the tanks for storage and treatment. These tanks were taken out of service in the 1970s. Based on the structure integrity of GAAT evaluated in 1995, the worst-case scenario for the tanks, even assuming they are in good condition, is to remain empty. A recently completed interim action conducted from April 1997 through September 2000 removed the tank liquids and residual solids to the extent practical. Interior video surveys of the tanks indicated signs of degradation of the Gunite material. The tanks continued to receive inleakage, which generated a relatively high volume waste stream that required periodic removal, treatment, and disposal. For these reasons, DOE chose in-place stabilization of Tanks W-3 through W-10 as a non-timecritical removal action under Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Tank stabilization activities involved removal of liquid from inleakage and placement of a grout mixture or ''flowable fill'' into the tanks to within 3-ft of the ground surface. Bechtel Jacobs Company, LLC (BJC) awarded Safety and Ecology Corporation (SEC) a subcontract in March 2001 to complete the documentation and fieldwork necessary to achieve tank stabilization in

  11. Project management plan for the gunite and associated tanks treatability studies project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1995-12-01

    This plan for the Gunite and Associated Tanks (GAAT) Treatability Studies Project satisfies the requirements of the program management plan for the Oak Ridge National Laboratory (ORNL) Environmental Restoration (ER) Program as established in the Program Management Plan for the Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory Site Environmental Restoration Program. This plan is a subtier of several other ER documents designed to satisfy the US Department of Energy (DOE) Order 4700.1 requirement for major systems acquisitions. This project management plan identifies the major activities of the GAAT Treatability Studies Project; establishes performance criteria; discusses the roles and responsibilities of the organizations that will perform the work; and summarizes the work breakdown structure, schedule, milestones, and cost estimate for the project.

  12. Treatment, storage, and disposal alternatives for the gunite and associated tanks at the Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    DePew, R.E.; Rickett, K.; Redus, K.S.; DuMont, S.P.; Lewis, B.E.; DePaoli, S.M.; Van Hoesen, S.D. Jr.

    1996-05-01

    The gunite and associated tanks (GAAT) are inactive, liquid low-level waste tanks located in and around the North and South Tank Farms at Oak Ridge National Laboratory. These underground tanks are the subject of an ongoing treatability study that will determine the best remediation alternatives for the tanks. As part of the treatability study, an assessment of viable treatment, storage, and disposal (TSD) alternatives has been conducted. The report summarizes relevant waste characterization data and statistics obtained to date. The report describes screening and evaluation criteria for evaluating TSD options. Individual options that pass the screening criteria are described in some detail. Order-or-magnitude cost estimates are presented for each of the TSD system alternatives. All alternatives are compared to the baseline approach of pumping all of the GAAT sludge and supernate to the Melton Valley Storage Tank (MVST) facility for eventual TSD along with the existing MOST waste. Four TSD systems are identified as alternatives to the baseline approach. The baseline is the most expensive of the five identified alternatives. The least expensive alternative is in-situ grouting of all GAAT sludge followed by in-situ disposal. The other alternatives are: (1) ex-situ grouting with on-site storage and disposal at Nevada Test Site (NTS); (2) ex-situ grouting with on-site storage and disposal at NTS and the Waste Isolation Pilot Plant (WIPP); and (3) ex-situ vitrification with on-site storage and disposal at NTS and WIPP.

  13. Functions and requirements for a waste dislodging and conveyance system for the gunite and associated tanks treatability study at Oak Ridge National Laboratory

    SciTech Connect

    Potter, J.D.; Mullen, O.D.

    1997-02-01

    Since the mid 1940s, the Department of Defense (DOD) and the Department of Energy (DOE) have conducted research and development activities at the Oak Ridge National Laboratory (ORNL) in support of urgent national interests in the fields of nuclear weaponry and nuclear energy. Some of these activities resulted in radiologically hazardous waste being temporarily deposited at ORNL, Waste Area Grouping 1. At this location, waste is stored in several underground storage tanks, awaiting ultimate final disposal. There are tanks of two basic categories. One category is referred to as the gunite tanks, the other category is associated tanks. The ORNL Gunite and Associated Tanks Treatability Study (GAAT TS) project was initiated in FY 1994 to support a record of decision in selecting from seven different options of technologies for retrieval and remediation of these tanks. As part of this decision process, new waste retrieval technologies will be evaluated at the 25-foot diameter gunite tanks in the North tank farm. Work is currently being conducted at Hanford and the University of Missouri-Rolla to evaluate and develop some technologies having high probability of being most practical and effective for the dislodging and conveying of waste from underground storage tanks. The findings of these efforts indicate that a system comprised of a dislodging end effector employing jets of high-pressure fluids, coupled to a water-jet conveyance system, all carried above the waste by a mechanical arm or other mechanism, is a viable retrieval technology for the GAAT TS tasks.

  14. Development of a waste dislodging and retrieval system for use in the Oak Ridge National Laboratory gunite tank

    SciTech Connect

    Randolph, J.D.; Lloyd, P.D.; Burks, B.L.

    1997-03-01

    As part of the Gunite And Associated Tanks (GAAT) Treatability Study the Oak Ridge National Laboratory (ORNL) has developed a tank waste retrieval system capable of removing wastes varying from liquids to thick sludges. This system is also capable of scarifying concrete walls and floors. The GAAT Treatability Study is being conducted by the Department of Energy Oak Ridge Environmental Restoration Program. Much of the technology developed for this project was cosponsored by the DOE Office of Science and Technology through the Tanks Focus Area (TFA) and the Robotics Technology Development Program. The waste dislodging and conveyance (WD&C) system was developed jointly by ORNL and participants from the TFA. The WD&C system is comprised of a four degree-of-freedom arm with back driveable motorized joints. a cutting and dislodging tool, a jet pump and hose management system for conveyance of wastes, confined sluicing end-effector, and a control system, and must be used in conjunction with a robotic arm or vehicle. Other papers have been submitted to this conference describing the development and operation of the arm and vehicle positioning systems. This paper will describe the development of the WD&C system and its application for dislodging and conveyance of ORNL sludges from the GAAT tanks. The confined sluicing end-effector relies on medium pressure water jets to dislodge waste that is then pumped by the jet pump through the conveyance system out of the tank. This paper will describe the results of cold testing of the integrated system. At the conference presentation there will also be results from the field deployment. ORNL has completed fabrication of the WD&C system for waste removal and is full-scale testing, including testing of the confined sluicing end-effector.

  15. Project health and safety plan for the Gunite and Associated Tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Abston, J.P.

    1997-04-01

    The Lockheed Martin Energy Systems, Inc. (Energy Systems) policy is to provide a safe and healthful workplace for all employees and subcontractors. The accomplishment of this policy requires that operations at the Gunite and Associated Tanks (GAAT) in the North and South Tank Farms (NTF and STF) at the Department of Energy (DOE) Oak Ridge National Laboratory are guided by an overall plan and consistent proactive approach to health and safety (H and S) issues. The policy and procedures in this plan apply to all GAAT operations in the NTF and STF. The provisions of this plan are to be carried out whenever activities identifies s part of the GAAT are initiated that could be a threat to human health or the environment. This plan implements a policy and establishes criteria for the development of procedures for day-to-day operations to prevent or minimize any adverse impact to the environment and personnel safety and health and to meet standards that define acceptable management of hazardous and radioactive materials and wastes. The plan is written to utilize past experience and best management practices in order to minimize hazards to human health or the environment from events such as fires, explosions, falls, mechanical hazards, or any unplanned release of hazardous or radioactive materials to the air. This plan explains additional task-specific health and safety requirements such as the Site Safety and health Addendum and Activity Hazard Analysis, which should be used in concert with this plan and existing established procedures.

  16. Results of Fall 1994 sampling of gunite and associated tanks at the Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1995-06-01

    This Technical Memorandum, was developed under Work Breakdown Structure 1.4.12.6.1.01.41.12.02. 11 (Activity Data Sheet 3301, ``WAG 1``). This document provides the Environmental Restoration Program with analytical results from liquid and sludge samples from the Gunite and Associated Tanks (GAAT). Information provided in this report forms part of the technical basis for criticality safety, systems safety, engineering design, and waste management as they apply to the GAAT treatability study and remediation.

  17. Functions and requirements for a waste dislodging and conveyance system for the Gunite and Associated Tanks Treatability Study at Oak Ridge National Laboratory

    SciTech Connect

    Potter, J.D.; Mullen, O.D.

    1995-09-01

    Functions and requirements for the Waste Dislodging and Conveyance System to be deployed in Gunite and Associated Tanks (GAAT) and tested and evaluated as a candidate tank waste retrieval technology by the GAAT Treatability Study (GAAT TS).

  18. Structural analysis of underground gunite storage tanks. Environmental Restoration Program

    SciTech Connect

    1995-08-01

    This report documents the structural analysis of the 50-ft diameter underground gunite storage tanks constructed in 1943 and located in the Oak Ridge National Laboratory (ORNL) South Tank Farm, known as Facility 3507 in the 3500-3999 area. The six gunite tanks (W-5 through W-10) are spaced in a 2 {times} 3 matrix at 60 ft on centers with 6 ft of soil cover. Each tank (Figures 1, 2, and 3) has an inside diameter of 50 ft, a 12-ft vertical sidewall having a thickness of 6 in. (there is an additional 1.5-in. inner liner for much of the height), and a spherical domed roof (nominal thickness is 10 in.) rising another 6 ft, 3 in. at the center of the tank. The thickness of both the sidewall and the domed roof increases to 30 in. near their juncture. The tank floor is nominally 3-in. thick, except at the juncture with the wall where the thickness increases to 9 in. The tanks are constructed of gunite (a mixture of Portland cement, sand, and water in the form of a mortar) sprayed from the nozzle of a cement gun against a form or a solid surface. The floor and the dome are reinforced with one layer of welded wire mesh and reinforcing rods placed in the radial direction. The sidewall is reinforced with three layers of welded wire mesh, vertical {1/2}-in. rods, and 21 horizontal rebar hoops (attached to the vertical rods) post-tensioned to 35,000 psi stress. The haunch at the sidewall/roof junction is reinforced with 17 horizontal rebar hoops post-tensioned with 35,000 to 40,000 psi stress. The yield strength of the post-tensioning steel rods is specified to be 60,000 psi, and all other steel is 40,000 psi steel. The specified 28-day design strength of the gunite is 5,000 psi.

  19. Basis for Selection of a Residual Waste Retrieval System for Gunite and Associated Tank W-9 at the Oak Ridge National Laboratory

    SciTech Connect

    Lewis, B.E

    2000-10-23

    Waste retrieval and transfer operations at the Gunite{trademark} and Associated Tanks (GAATs) Remediation Project have been successfully accomplished using the Tank Waste Retrieval System. This system is composed of the Modified Light-Duty Utility Arm, Houdini Vehicle, Waste Dislodging and Conveyance System, Hose Management Arm, and Sludge Conditioning System. GAAT W-9 has been used as a waste-consolidation and batch-transfer tank during the retrieval of sludges and supernatants from the seven Gunite tanks in the North and South tank farms at Oak Ridge National Laboratory. Tank W-9 was used as a staging tank for the transfers to the Melton Valley Storage Tanks (MVSTs). A total of 18 waste transfers from W-9 occurred between May 25, 1999, and March 30, 2000. Most of these transfers were accomplished using the PulsAir Mixer to mobilize and mix the slurry and a submersible retrieval-transfer pump to transfer the slurry through the Sludge Conditioning System and the {approx}1-mile long, 2-in.-diam waste-transfer line to the MVSTs. The transfers from W-9 have consisted of low-solids-content slurries with solids contents ranging from {approx}2.8 to 6.8 mg/L. Of the initial {approx}88,000 gal of wet sludge estimated in the GAATs, a total of {approx}60,451 gal have been transferred to the MVSTs via tank W-9 as of March 30, 2000. Once the waste-consolidation operations and transfers from W-9 to the MVSTs are completed, the remaining material in W-9 will be mobilized and transferred to the active waste system, Bethel Valley Evaporator Service Tank W-23. Tank W-23 will serve as a batch tank for the final waste transfers from tank W-9 to the MVSTs. This report provides a summary of the requirements and recommendations for the final waste retrieval system for tank W-9, a compilation of the sample analysis data for the sludge in W-9, and brief descriptions of the various waste-retrieval system concepts that were considered for this task. The recommended residual waste retrieval

  20. GLASS FEASIBILITY STUDY: VITRIFICATION OF OAK RIDGE NATIONAL LABORATORY GUNITE WASTE USING IRON PHOSPHATE GLASS (U)

    SciTech Connect

    Fellinger, T.

    1996-03-01

    This report describes the results of a glass feasibility study on vitrification of Oak Ridge National Laboratory (ORNL) Gunite waste into an Iron Phosphate glass. This glass feasibility study is part of a larger ORNL Gunite and Associated Tanks Treatability program (TTPSR1-6-WT-31). The treatability program explores different immobilization techniques of placing Gunite waste into a glass or grout form for long term storage. ORNL Gunite tanks contain waste that originated from years of various ORNL Research and Development programs. The available analyses of the Gunite Waste Tanks indicate, uranium and/or thorium as the dominant chemical constituent (50% +) and Cs{sup 137} the primary radionuclide. This information was utilized in determining a preliminary iron phosphate glass formulation. Chemical and physical properties: processing temperature, waste loading capability, chemical durability, density and redox were determined.

  1. Treatability study operational testing program and implementation plan for the Gunite and Associated Tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1996-03-01

    This Treatability Study (TS) Operational Testing Program and Implementation Plan identifies operational testing to be performed to: (1) Demonstrate the technical feasibility of methods proposed for the removal of radiochemical sludge heels from the underground storage tanks located at Oak Ridge National Laboratory (ORNL), known as the Gunite and Associated Tanks (GAAT) Operable Unit (OU). (The bulk of the radiochemical waste, which was previously stored in the tanks, was removed during the 1980s, and only a sludge heel remains.) (2) Reduce the uncertainty in meeting the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requirements for the GAAT OU. (3) Minimize the overall costs to accomplish the first two objectives. An initial Feasibility Study (FS) effort identified uncertainties in the evaluation of various alternatives for addressing the remediation of the GAAT OU. To support future decision making, the US. Department of Energy is performing a TS to identify cost-effective remediation approaches for the GAAT OU by providing information to reduce cost and technical uncertainty and better define acceptable remediation strategies. The testing activities will be initially conducted in a nonradioactive environment at the Tanks Technology Cold Test Facility (TTCTF) at ORNL. This will permit the design and initial performance testing and training activities to be completed while minimizing the risk, employee exposure, and costs associated with the testing effort. The component design and functional testing and initial system performance testing will be completed in the TTCTF. After the component and initial system performance testing have been completed, the operations testing will continue in the North Tank Farm (NTF). This testing has an associated higher cost and risk, but is necessary to provide results for actual waste heel removal.

  2. Treatability Study Operational Testing Program and Implementation Plan for the Gunite and Associated Tanks at the Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1996-09-01

    To support future decision making of the Gunite and Associated Tanks (GAAT) Operable Unit (OU) remedy selection, the Department of Energy (DOE) is performing a Treatability Study (TS), consistent with the EPA guidance for Comprehensive Environmental Response, compensation, and Liability Act (CERCLA) treatability studies. The study will inform stakeholders about various waste removal technologies and the cost of potential remediation approaches, particularly the cost associated with sluicing and the reduction in risk to human health and the environment from tank content removal. As part of the GAAT OU remedy, a series of studies and technology tests will be preformed. These may address one or more of the following areas, characterization, removal, treatment, and transfer of wastes stored in the GAAT OU.

  3. Gunite and Associated Tanks Waste Conditioning System: Description and Operational Summary

    SciTech Connect

    Emison, JA

    2002-03-14

    The purpose of this report is to describe and document the function, operational performance, problems encountered, lessons-learned, and overall assessment of the performance of the waste conditioning system (WCS) in the Gunite{trademark} and Associated Tanks (GAAT) remediation project at the Oak Ridge National Laboratory (ORNL). The GAAT are located in the main plant area of ORNL in the North and South Tank Farms. These tanks were constructed in 1943 as part of the Manhattan Project during World War II. Each tank in the South Tank Farm (STF) has a 50-ft inside diameter and a capacity of {approx}170,000 gal. Each Gunite tank in the North Tank Farm (NTF) has a 25-ft inside diameter with a capacity of {approx}44,000 gal. The GAAT were designed to receive radioactive and chemical wastes from ORNL processes. The tanks were constructed of Gunite, which is created by pneumatically spraying concrete over a wire mesh. Following construction, the site was backfilled so the domes of the tanks were covered with {approx}6 ft of earth. The STF tanks (W-5, -6, -7, -8, -9, and -10) are set in a 2 x 3 array with an east-west axis. The two GAAT in the NTF are on the north side of Central Avenue, and the STF is across the street. One additional Gunite tank, TH-4, is located {approx}300 ft east of the STF. TH-4 is a smaller, 20-ft inside diameter tank with a capacity of {approx}14,000 gal. Approximately 90% of the sludge inventory was removed from the STF tanks during a sluicing campaign in 1982-84 (Autry et al., 1990). Over 95% of the residual from the original sluicing was removed during the GAAT Remediation Project of 1997-2000. The NTF and STF tanks, as well as tank TH-4 were remediated under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) with regulatory oversight by the U.S. Environmental Protection Agency (EPA) and the Tennessee Department of Environment and Conservation (TDEC).

  4. Russian Pulsating Mixer Pump Deployment in the Gunite and Associated Tanks at ORNL

    SciTech Connect

    Hatchell, Brian K.; Lewis, Ben; Johnson, Marshall A.; Randolph, J. G.

    2001-03-01

    In FY 1998, Pulsating Mixer Pump (PMP) technology, consisting of a jet mixer powered by a reciprocating air supply, was selected for deployment in one of the Gunite and Associated Tanks at Oak Ridge National Laboratory (ORNL) to mobilize settled solids. The pulsating mixer pump technology was identified during FY 1996 and FY 1997 technical exchanges between the U.S. Department of Energy (DOE) Tanks Focus Area Retrieval and Closure program, the DOE Environmental Management International Programs, and delegates from Russia as a promising technology that could be implemented in the DOE complex. During FY 1997, the pulsating mixer pump technology, provided by the Russian Integrated Mining Chemical Company, was tested at Pacific Northwest National Laboratory (PNNL) to observe its ability to suspend settled solids. Based on the results of this demonstration, ORNL and DOE staff determined that a modified pulsating mixer pump would meet project needs for remote sludge mobilization of Gunite tank sludge and reduce the cost of operation and maintenance of more expensive mixing systems. The functions and requirements of the system were developed by combining the results and recommendations from the pulsating mixer pump demonstration at PNNL with the requirements identified by staff at ORNL involved with the remediation of the Gunite and Associated Tanks. The PMP is comprised of a pump chamber, check valve, a working gas supply pipe, a discharge manifold, and four jet nozzles. The pump uses two distinct cycles, fill and discharge, to perform its mixing action. During the fill cycle, vacuum is applied to the pump chamber by an eductor, which draws liquid into the pump. When the liquid level inside the chamber reaches a certain level, the chamber is pressurized with compressed air to discharge the liquid through the jet nozzles and back into the tank to mobilize sludge and settled solids.

  5. Gunite and associated tanks remediation project recycling and waste minimization effort

    SciTech Connect

    Van Hoesen, S.D.; Saunders, A.D.

    1998-05-01

    The Department of Energy`s Environmental Management Program at Oak Ridge National Laboratory has initiated clean up of legacy waste resulting from the Manhattan Project. The gunite and associated tanks project has taken an active pollution prevention role by successfully recycling eight tons of scrap metal, reusing contaminated soil in the Area of Contamination, using existing water (supernate) to aid in sludge transfer, and by minimizing and reusing personal protective equipment (PPE) and on-site equipment as much as possible. Total cost savings for Fiscal Year 1997 activities from these efforts are estimated at $4.2 million dollars.

  6. Engineering development of waste retrieval end effectors for the Oak Ridge gunite waste tanks

    SciTech Connect

    Mullen, O.D.

    1997-05-01

    The Gunite and Associated Tanks Treatability Study at Oak Ridge National Laboratory selected the waterjet scarifying end effector, the jet pump conveyance system, and the Modified Light Duty Utility Arm and Houdini Remotely Operated Vehicle deployment and manipulator systems for evaluation. The waterjet-based retrieval end effector had been developed through several generations of test articles targeted at deployment in Hanford underground storage tanks with a large robotic arm. The basic technology had demonstrated effectiveness at retrieval of simulants bounding the foreseen range of waste properties and indicated compatibility with the planned deployment systems. The Retrieval Process Development and Enhancements team was tasked with developing a version of the retrieval end effector tailored to the Oak Ridge tanks, waste and deployment platforms. The finished prototype was delivered to PNNL and subjected to a brief round of characterization and performance testing at the Hydraulic Testbed prior to shipment to Oak Ridge. It has undergone extensive operational testing in the Oak Ridge National Laboratory Tanks Technology Cold Test Facility and performed well, as expected. A second unit has been delivered outfitted with the high pressure manifold.

  7. The Gunite and Associated Tanks Remediation Project Tank Waste Retrieval Performance and Lessons Learned, vol. 2 [of 2

    SciTech Connect

    Lewis, BE

    2003-10-07

    The Gunite and Associated Tanks (GAAT) Remediation Project was the first of its kind performed in the United States. Robotics and remotely operated equipment were used to successfully transfer almost 94,000 gal of remote-handled transuranic sludge containing over 81,000 Ci of radioactive contamination from nine large underground storage tanks at the Oak Ridge National Laboratory (ORNL). The sludge was transferred with over 439,000 gal of radioactive waste supernatant and {approx}420,500 gal of fresh water that was used in sluicing operations. The GAATs are located in a high-traffic area of ORNL near a main thoroughfare. Volume 1 provides information on the various phases of the project and describes the types of equipment used. Volume 1 also discusses the tank waste retrieval performance and the lessons learned during the remediation effort. Volume 2 consists of the following appendixes, which are referenced in Vol. 1: A--Background Information for the Gunite and Associated Tanks Operable Unit; B--Annotated Bibliography; C--GAAT Equipment Matrix; D--Comprehensive Listing of the Sample Analysis Data from the GAAT Remediation Project; and E--Vendor List for the GAAT Remediation Project. The remediation of the GAATs was completed {approx}5.5 years ahead of schedule and {approx}$120,435K below the cost estimated in the Remedial Investigation/Feasibility Study for the project. These schedule and cost savings were a direct result of the selection and use of state-of-the-art technologies and the dedication and drive of the engineers, technicians, managers, craft workers, and support personnel that made up the GAAT Remediation Project Team.

  8. Fabrication of a Sludge-Conditioning System for Processing Legacy Wastes from the Gunite and Associated Tanks

    SciTech Connect

    Randolph, J.D.; Lewis, B.E.; Farmer, J.R.; Johnson, M.A.

    2000-08-01

    The Sludge Conditioning System (SCS) for the Gunite and Associated Tanks (GAATs) is designed to receive, monitor, characterize and process legacy waste materials from the South Tank Farm tanks in preparation for final transfer of the wastes to the Melton Valley Storage Tanks (MVSTs), which are located at Oak Ridge National Laboratory. The SCS includes (1) a Primary Conditioning System (PCS) Enclosure for sampling and particle size classification, (2) a Solids Monitoring Test Loop (SMTL) for slurry characterization, (3) a Waste Transfer Pump to retrieve and transfer waste materials from GAAT consolidation tank W-9 to the MVSTs, (4) a PulsAir Mixing System to provide mixing of consolidated sludges for ease of retrieval, and (5) the interconnecting piping and valving. This report presents the design, fabrication, cost, and fabrication schedule information for the SCS.

  9. The Gunite and Associated Tanks Remediation Project Tank Waste Retrieval Performance and Lessons Learned, vol. 1 [of 2

    SciTech Connect

    Lewis, BE

    2003-10-07

    The Gunite and Associated Tanks (GAAT) Remediation Project was the first of its kind performed in the United States. Robotics and remotely operated equipment were used to successfully transfer almost 94,000 gal of remote-handled transuranic sludge containing over 81,000 Ci of radioactive contamination from nine large underground storage tanks at the Oak Ridge National Laboratory (ORNL). The sludge was transferred with over 439,000 gal of radioactive waste supernatant and {approx}420,500 gal of fresh water that was used in sluicing operations. The GAATs are located in a high-traffic area of ORNL near a main thoroughfare. A phased and integrated approach to waste retrieval operations was used for the GAAT Remediation Project. The project promoted safety by obtaining experience from low-risk operations in the North Tank Farm before moving to higher-risk operations in the South Tank Farm. This approach allowed project personnel to become familiar with the tanks and waste, as well as the equipment, processes, procedures, and operations required to perform successful waste retrieval. By using an integrated approach to tank waste retrieval and tank waste management, the project was completed years ahead of the original baseline schedule, which resulted in avoiding millions of dollars in associated costs. This report is organized in two volumes. Volume 1 provides information on the various phases of the GAAT Remediation Project. It also describes the different types of equipment and how they were used. The emphasis of Volume 1 is on the description of the tank waste retrieval performance and the lessons learned during the GAAT Remediation Project. Volume 2 provides the appendixes for the report, which include the following information: (A) Background Information for the Gunite and Associated Tanks Operable Unit; (B) Annotated Bibliography; (C) Comprehensive Listing of the Sample Analysis Data from the GAAT Remediation Project; (D) GAAT Equipment Matrix; and (E) Vendor List

  10. Performance Assessment of the Waste Dislodging Conveyance System During the Gunite And Associated Tanks Remediation Project

    SciTech Connect

    Lloyd, P.D.

    2001-02-21

    The Waste Dislodging and Conveyance System (WD and CS) and other components of the Tank Waste Retrieval System (TWRS) were developed to address the need for removal of hazardous wastes from underground storage tanks (USTs) in which radiation levels and access limitations make traditional waste retrieval methods impractical. Specifically, these systems were developed for cleanup of the Gunite and Associated Tanks (GAAT) Operable Unit (OU) at the Oak Ridge National Laboratory (ORNL). The WD and CS is comprised of a number of different components. The three primary hardware subsystems are the Hose Management System (HMS), the Confined Sluicing End-Effector (CSEE), and the Flow Control Equipment and Containment Box (FCE/CB). In addition, a Decontamination Spray Ring (DSR) and a control system were developed for the system. The WD and CS is not a stand-alone system; rather, it is designed for deployment with either a long-reach manipulator like the Modified Light Duty Utility Arm (MLDUA) or a remotely operated vehicle system such as the Houdini{trademark}. The HMS was designed to act as a pipeline for the transfer of dislodged waste; as a hose-positioning and tether-management system; and as a housing for process equipment such as the water-powered jet pump that provides the necessary suction to vacuum slurried waste from the UST. The HMS was designed to facilitate positioning of an end-effector at any point within the 25-ft- or 50-ft-diameter USTs in the GAAT OU.

  11. Field performance of the waste retrieval end effectors in the Oak Ridge gunite tanks

    SciTech Connect

    Mullen, O.D.

    1997-09-01

    Waterjet-based tank waste retrieval end effectors have been developed by Retrieval Process Development and Enhancements through several generations of test articles targeted at deployment in Hanford underground storage tanks with a large robotic arm. The basic technology has demonstrated effectiveness for retrieval of simulants bounding a wide range of waste properties and compatibility with foreseen deployment systems. The Oak Ridge National Laboratory (ORNL) selected the waterjet scarifying end effector, the jet pump conveyance system, and the Modified Light Duty Utility Arm and Houdini Remotely Operated Vehicle deployment and manipulator systems for evaluation in the Gunite and Associated Tanks Treatability Study (GAAT-TS). The Retrieval Process Development and Enhancements (RPD&E) team was tasked with developing a version of the retrieval end effector tailored to the Oak Ridge tanks, waste, and deployment platforms. The conceptual design was done by the University of Missouri-Rolla in FY 1995-96. The university researchers conducted separate effects tests of the component concepts, scaled the basic design features, and constructed a full-scale test article incorporating their findings in early FY 1996. The test article was extensively evaluated in the Hanford Hydraulic Testbed and the design features were further refined. Detail design of the prototype item was started at Waterjet Technology, Inc. before the development testing was finished, and two of the three main subassemblies were substantially complete before final design of the waterjet manifold was determined from the Hanford hydraulic testbed (HTB) testing. The manifold on the first prototype was optimized for sludge retrieval; assembled with that manifold, the end effector is termed the Sludge Retrieval End Effector (SREE).

  12. Gunite Scarifying End Effector. Innovative Technology Summary Report

    SciTech Connect

    2001-09-01

    The Gunite Scarifying End Effector (GSEE) is designed to remove a layer of the gunite tank walls, which are contaminated with radioactivity. Removing this radioactivity is necessary to close the tank.

  13. Use of the Modified Light Duty Utility Arm to Perform Nuclear Waste Cleanup of Underground Waste Storage Tanks at Oak Ridge National Laboratory

    SciTech Connect

    Blank, J.A.; Burks, B.L.; DePew, R.E.; Falter, D.D.; Glassell, R.L.; Glover, W.H.; Killough, S.M.; Lloyd, P.D.; Love, L.J.; Randolph, J.D.; Van Hoesen, S.D.; Vesco, D.P.

    1999-04-01

    The Modified Light Duty Utility Arm (MLDUA) is a selectable seven or eight degree-of-freedom robot arm with a 16.5 ft (5.03 m) reach and a payload capacity of 200 lb. (90.72 kg). The utility arm is controlled in either joystick-based telerobotic mode or auto sequence robotics mode. The MLDUA deployment system deploys the utility arm vertically into underground radioactive waste storage tanks located at Oak Ridge National Laboratory. These tanks are constructed of gunite material and consist of two 25 ft (7.62 m) diameter tanks in the North Tank Farm and six 50 ft (15.24 m) diameter tanks in the South Tank Farm. After deployment inside a tank, the utility arm reaches and grasps the confined sluicing end effecter (CSEE) which is attached to the hose management arm (HMA). The utility arm positions the CSEE within the tank to allow the HMA to sluice the tank's liquid and solid waste from the tank. The MLDUA is used to deploy the characterization end effecter (CEE) and gunite scarifying end effecter (GSEE) into the tank. The CEE is used to survey the tank wall's radiation levels and the physical condition of the walls. The GSEE is used to scarify the tank walls with high-pressure water to remove the wall scale buildup and a thin layer of gunite which reduces the radioactive contamination that is embedded into the gunite walls. The MLDUA is also used to support waste sampling and wall core-sampling operations. Other tools that have been developed for use by the MLDUA include a pipe-plugging end effecter, pipe-cutting end effecter, and pipe-cleaning end effecter. Washington University developed advance robotics path control algorithms for use in the tanks. The MLDUA was first deployed in June 1997 and has operated continuously since then. Operational experience in the first four tanks remediated is presented in this paper.

  14. Status and Needs for Tank Isolation System Contingencies at the Oak Ridge National Laboratory

    SciTech Connect

    Chesser, J.B.

    2000-02-02

    This document assesses the need for additional tank isolation systems and tooling at the Oak Ridge National Laboratory (ORNL). Locations for future operations at ORNL include the South and North Tank Farms and various Federal Facilities Agreement tanks. The goal of this report is to identify future needs for development of remote tools and systems to isolate inactive waste storage tanks. Remote tools have been developed to support waste-retrieval and tank-isolation operations at the Gunite and Associated Tanks (GAATs) at ORNL. The tools developed for in-tank remote operations include a pipe-cutting tool (a modified band saw), a pipe-cleaning tool (a modified drill with a wire brush), and a pipe plug. A review of the planned future operations revealed several desirable modifications to improve the efficiency, operability, and flexibility of the existing tank-isolation tools. For example, the pipe-cutting tool needs improvements to provide better alignment, a blade-cutting-release device, improved tire replacement, sensors to prevent operation of the saw when the blade stops, blade speed controls, and force feedback sensors. In addition, the need to test the existing pipe plug for use on corroded piping was identified. The pipe plug has been used on only relatively clean in-tank stainless steel (SS) piping to date. However, there may be a need later to use the plug on corroded SS and other types of pipes. Improvements to the pipe plug for use on flush wall pipes and small-diameter openings in tanks are also desirable. Besides tank isolation, those performing tank closures may need to use cutting and capping equipment on buried pipes. The current cutting and capping equipment may have to be modified for deployment systems other than the Modified Light Duty Utility Arm, for which they were initially designed. Improved cutting and other remote systems may also be needed to dispose of contaminated equipment and tank shells. These requirements will be defined jointly by

  15. Summary report for the tank tightness testing of underground storage tanks, Idaho National Engineering Laboratory

    SciTech Connect

    Not Available

    1990-03-01

    Between August 14, 1989, and August 26, 1989, 16 underground storage tanks were tank tightness tested for leaks as part of the Idaho National Engineering Laboratory tank management program. This report summarizes the results of these tank tightness tests, the modifications and repairs made to the tank systems, fuel transfer records, and any problems that affected the tank testing schedule. Of the 16 underground storage tanks tested, five failed the tank tightness test. Attempts were made to repair the tanks that failed the tank tightness test. Of those tanks, two were tested three times (one passed and one failed), and three were tested twice (two passed and one failed). The five failed tanks were removed and will be replaced with tanks that meet the Environmental Protection Agency regulations of underground storage tanks. 3 refs., 1 fig., 3 tabs.

  16. Potential radiological exposure rates resulting from hypothetical dome failure at Tank W-10

    SciTech Connect

    Not Available

    1994-07-01

    The main plant area at Oak Ridge National Laboratory (ORNL) contains 12 buried Gunite tanks that were used for the storage and transfer of liquid radioactive waste. Although the tanks are no longer in use, they are known to contain some residual contaminated sludges and liquids. In the event of an accidental tank dome failure, however unlikely, the liquids, sludges, and radioactive contaminants within the tank walls themselves could create radiation fields and result in above-background exposures to workers nearby. This Technical Memorandum documents a series of calculations to estimate potential radiological exposure rates and total exposures to workers in the event of a hypothetical collapse of a Gunite tank dome. Calculations were performed specifically for tank W-10 because it contains the largest radioactivity inventory (approximately half of the total activity) of all the Gunite tanks. These calculations focus only on external, direct gamma exposures for prescribed, hypothetical exposure scenarios and do not address other possible tank failure modes or routes of exposure. The calculations were performed with established, point-kernel gamma ray modeling codes.

  17. Tank waste removal using a high pressure waterjet system

    SciTech Connect

    Randolph, J.D.; Rinker, M.W.; Summers, D.

    1996-10-01

    The Oak Ridge National Laboratory has several tank wastes that are currently stored in inactive tanks constructed of gunite concrete. A remediation program at ORNL and a development program at PNL and UMR are collaborating to develop a system that will utilize high pressure waterjet technology for cutting and dislodging sludge beds, and for conveyance of those materials to a treatment tank. This technology for waste removal has two major advantages. First, sludge will be retrieved from one or more high risk tanks, that is tanks with a high degree of uncertainty for failure, to a single treatment tank with lower risk. Second, sludges of similar nature will be consolidated for volume reduction. ORNL and PNL are currently pursuing this technology for waste removal and transport to a single immobilization treatment facility. The ORNL remediation program is known as the Gunite And Associated Tanks Treatability Study. The PNL development program is known as Retrieval Process Development and Enhancement. UMR is developing the waste dislodging/cutting tool. This paper will describe the waterjet technology for waste dislodging and conveyance of ORNL sludges from underground storage tanks.

  18. EXPERIMENTS ON BUOYANT PLUME DISPERSION IN A LABORATORY CONVENTION TANK

    EPA Science Inventory

    Buoyant plume dispersion in the convective boundary layer (CBL) is investigated experimentally in a laboratory convection tank. The focus is on highly-buoyant plumes that loft near the CBL capping inversion and resist downward mixing. Highly- buoyant plumes are those with dimen...

  19. Linear Scarifying End-Effector Developed For Wall Cleaning In Underground Storage Tanks

    SciTech Connect

    Fitzgerald, C.L.F.

    2001-02-04

    This paper describes the development and performance of a Linear Scarifying End-Effector (LSEE) designed and fabricated for deployment by a remotely operated vehicle. The end-effector was designed to blast or scarify in-grained residual contamination from gunite tank walls using high-pressure water jets after the bulk sludge had been removed from the tanks using an integrated suite of remotely operated tools. Two generations of the LSEE were fabricated, tested, and deployed in the gunite tanks at the Oak Ridge National Laboratory, with varying levels of success. Because the LSEE was designed near the end of a four-year project to clean up the gunite tanks at Oak Ridge, a number of design constraints existed. The end-effector had to utilize pneumatic, hydraulic and electrical interfaces already available at the site; and to be deployable through one of the containment structures already in place for the other remote systems. Another primary design consideration was that the tool had to effectively extend the reach of an existing remotely operated vehicle from six ft. to at least ten ft. to allow cleaning the tank walls from floor to ceiling. In addition, the combined weight and thrust of the LSEE had to be manageable by the manipulator mounted on the vehicle. Finally, the end-effector had to follow an autonomous scarifying path such that the vehicle was only required to reposition the unit at the end of each pass after the mist had cleared from the tank. The prototypes successfully met each of these challenges, but did encounter other difficulties during actual tank operations.

  20. 73. View of canal, gunite lined, with turnout gates. Photographer ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    73. View of canal, gunite lined, with turnout gates. Photographer Mark Durben. Source: Salt River Project. - Waddell Dam, On Agua Fria River, 35 miles northwest of Phoenix, Phoenix, Maricopa County, AZ

  1. Laboratory Evaluation of Nitrile Fuel Tank Materials (Phase 2)

    DTIC Science & Technology

    2013-09-01

    control number . PLEASE DO NOT RETURN YOUR FORM TO THE ABOVE ADDRESS. 1. REPORT DATE (DD-MM-YYYY) September 2013 2. REPORT TYPE Final 3. DATES...COVERED (From - To) October 2011–March 2013 4. TITLE AND SUBTITLE Laboratory Evaluation of Nitrile Fuel Tank Materials (Phase II) 5a. CONTRACT NUMBER ...5b. GRANT NUMBER 5c. PROGRAM ELEMENT NUMBER 6. AUTHOR(S) James M. Sloan, David Flanagan, Daniel DeSchepper, Paul Touchet,* and Henry Feuer† 5d

  2. Status and needs for tank isolation system contingencies at the Oak Ridge National Laboratory

    SciTech Connect

    Chesser, J.B.; Lewis, B.E.

    2000-01-01

    This document assesses the need for additional tank isolation systems and tooling at the Oak Ridge National Laboratory (ORNL). Locations for future operations at ORNL include the South and North Tank Farms and various Federal Facilities Agreement tanks. The goal of this report is to identify future needs for development of remote tools and systems to isolate inactive waste storage tanks.

  3. Shoaling Large Amplitude Internal Solitary Waves in a Laboratory Tank

    NASA Astrophysics Data System (ADS)

    Allshouse, Michael; Larue, Conner; Swinney, Harry

    2014-11-01

    The shoaling of internal solitary waves onto the continental shelf can change both the wave dynamics and the state of the environment. Previous observations have demonstrated that these waves can trap fluid and transport it over long distances. Through the use of a camshaft-based wavemaker, we produce large amplitude shoaling waves in a stratified fluid in a laboratory tank. Simulations of solitary waves are used to guide the tuning of the wave generator to approximate solitary waves; thus nonlinear waves can be produced within the 4m long tank. PIV and synthetic schlieren measurements are made to study the transport of fluid by the wave as it moves up a sloping boundary. The results are then compared to numerical simulations and analyzed using finite time Lyapunov exponent calculations. This Lagrangian analysis provides an objective measure of barriers surrounding trapped regions in the flow. Supported by ONR MURI Grant N000141110701 (WHOI).

  4. Inactive tanks remediation program strategy and plans for Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1997-03-01

    This report presents plans and strategies for remediation of the liquid low-level waste (LLLW) tanks that have been removed from service (also known as inactive tanks) at Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. These plans and strategies will be carried out by the Environmental Restoration Program`s Inactive LLLW Tank Program at ORNL. These tanks are defined as Category D tanks because they are existing tank systems without secondary containment that are removed from service. The approach to remediation of each tank or tank farm must be adapted in response to the specific circumstances of individual tank sites. The approach will be tailored to accommodate feedback on lessons learned from previous tank remediation activities and will not be a rigid step-by-step approach that must be conducted identically for every tank system. However, the approach will follow a multistep decision process. The overall objective of the Inactive Tank Program is to remediate all LLLW tanks that have been removed from service to the extent practicable in accordance with the FFA requirements. The Inactive Tank Program will focus on the remediation of the tank residues (i.e., contents after tank has been emptied) and tank shell. This strategy is discussed in detail in this report.

  5. Design demonstrations for category B tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Not Available

    1994-11-01

    This document presents design demonstrations conducted of liquid low-level waste (LLLW) storage tank systems located at the Oak Ridge National Laboratory (ORNL). Demonstration of the design of these tank systems has been stipulated by the Federal Facility Agreement (FFA) between the US Environmental Protection Agency (EPA)-Region IV; the Tennessee Department of Environment and Conservation (TDEC); and the DOE. The FFA establishes four categories of tanks. These are: Category A -- New or replacement tank systems with secondary containment; Category B -- Existing tank systems with secondary containment; Category C -- Existing tank systems without secondary containment; Category D -- Existing tank systems without secondary containment that are removed from service. This document provides a design demonstration of the secondary containment and ancillary equipment of 11 tank systems listed in the FFA as Category B. The design demonstration for each tank is presented.

  6. 12. DETAIL INDICATING TRANSITION FROM ORIGINAL SURFACE TO GUNITE OVERLAY ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    12. DETAIL INDICATING TRANSITION FROM ORIGINAL SURFACE TO GUNITE OVERLAY ON UPSTREAM EMBANKMENT OF DAM (FROM REPAIRS COMPLETED IN 1977) - Upper Doughty Dam, 200 feet west of Garden State Parkway, 1.7 miles west of Absecon, Egg Harbor City, Atlantic County, NJ

  7. Inactive tanks remediation program strategy and plans for Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1997-11-01

    This report presents plans and strategies for remediation of the liquid low-level waste (LLLW) tanks that have been removed from service (also known as inactive tanks) at Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. These plans and strategies will be carried out by the Environmental Restoration Program`s Inactive LLLW Tank Program at ORNL. The approach to remediation of each tank or tank farm must be adapted in response to the specific circumstances of individual tank sites. The approach will be tailored to accommodate feedback on lessons learned from previous tank remediation activities and will not be a rigid step-by-step approach that must be conducted identically for every tank system. However, the approach will follow a multistep decision process. The overall objective of the Inactive Tank Program is to remediate all LLLW tanks that have been removed from service to the extent practicable in accordance with the FFA requirements. The Inactive Tank Program will focus on the remediation of the tank residues and tank shell. This strategy is discussed in detail in this report.

  8. Corrosion analysis of decommissioned carbon steel waste water tanks at Brookhaven National Laboratory

    SciTech Connect

    Soo, P.; Roberts, T.C.

    1995-07-01

    A corrosion analysis was carried out on available sections of carbon steels taken from two decommissioned radioactive waste water tanks at Brookhaven National Laboratory. One of the 100,000 gallon tanks suffered from a pinhole failure in the wall which was subsequently patched. From the analysis it was shown that this leak, and two adjacent leaks were initiated by a discarded copper heating coil that had been dropped into the tank during service. The failure mechanism is postulated to have been galvanic attack at points of contact between the tank structure and the coil. Other leaks in the two tanks are also described in this report.

  9. Grout and glass performance in support of stabilization/solidification of ORNL tank sludges

    SciTech Connect

    Spence, R.D.; Mattus, C.H.; Mattus, A.J.

    1998-09-01

    Wastewater at Oak Ridge National Laboratory (ORNL) is collected, evaporated, and stored in the Melton Valley Storage Tanks (MVST) and Bethel Valley Evaporator Storage Tanks (BVEST) pending treatment for disposal. In addition, some sludges and supernatants also requiring treatment remain in two inactive tank systems: the gunite and associated tanks (GAAT) and the old hydrofracture (OHF) tank. The waste consists of two phases: sludge and supernatant. The sludges contain a high amount of radioactivity, and some are classified as TRU sludges. Some Resource Conservation and Recovery Act (RCRA) metal concentrations are high enough to be defined as RCRA hazardous; therefore, these sludges are presumed to be mixed TRU waste. Grouting and vitrification are currently two likely stabilization/solidification alternatives for mixed wastes. Grouting has been used to stabilize/solidify hazardous and low-level radioactive waste for decades. Vitrification has been developed as a high-level radioactive alternative for decades and has been under development recently as an alternative disposal technology for mixed waste. The objective of this project is to define an envelope, or operating window, for grout and glass formulations for ORNL tank sludges. Formulations will be defined for the average composition of each of the major tank farms (BVEST/MVST, GAAT, and OHF) and for an overall average composition of all tank farms. This objective is to be accomplished using surrogates of the tank sludges with hot testing of actual tank sludges to check the efficacy of the surrogates.

  10. Asymmetry of wind waves studied in a laboratory tank

    NASA Astrophysics Data System (ADS)

    Leykin, I. A.; Donelan, M. A.; Mellen, R. H.; McLaughlin, D. J.

    Asymmetry of wind waves was studied in laboratory tank tinder varied wind and fetch conditions using both bispectral analysis of wave records and third-order statistics of the surface elevation. It is found skewness S (the normalized third-order moment of surface elevation describing the horizontal asymmetry waves) varies only slightly with the inverse wave u*/Cm (where u* is the air friction velocity and Cm is phase speed of the dominant waves). At the same time asymmetry A, which is determined from the Hilbert transform of the wave record and characterizes the skewness of the rate of change of surface elevation, increase consistently in magnitude with the ratio u*/Cm. This suggests that nonlinear distortion of the wave profile determined by the degree of wind forcing and is a sensitive indicator of wind-wave interaction processes. It is shown that the asymmetric profile of waves can described within the frameworks of the nonlinear nonspectral concept (Plate, 1972; Lake and Yuen, 197 according to which the wind-wave field can be represented as a coherent bound-wave system consisting mainly of dominant component w. and its harmonics propagating with the same speed C. , as observed by Ramamonjiaris and Coantic (1976). The phase shift between o). harmonics is found and shown to increase with the asymmetry of the waves.

  11. Asymmetry of wind waves studied in a laboratory tank

    NASA Astrophysics Data System (ADS)

    Ileykin, L. A.; Donelan, M. A.; Mellen, R. H.; McLaughlin, D. J.

    1995-03-01

    Asymmetry of wind waves was studied in laboratory tank tinder varied wind and fetch conditions using both bispectral analysis of wave records and third-order statistics of the surface elevation. It is found skewness S (the normalized third-order moment of surface elevation describing the horizontal asymmetry waves) varies only slightly with the inverse wave u*/Cm (where u* is the air friction velocity and Cm is phase speed of the dominant waves). At the same time asymmetry A, which is determined from the Hilbert transform of the wave record and characterizes the skewness of the rate of change of surface elevation, increase consistently in magnitude with the ratio u*/Cm. This suggests that nonlinear distortion of the wave profile determined by the degree of wind forcing and is a sensitive indicator of wind-wave interaction processes. It is shown that the asymmetric profile of waves can described within the frameworks of the nonlinear nonspectral concept (Plate, 1972; Lake and Yuen, 197 according to which the wind-wave field can be represented as a coherent bound-wave system consisting mainly of dominant component w. and its harmonics propagating with the same speed C. , as observed by Ramamonjiaris and Coantic (1976). The phase shift between o). harmonics is found and shown to increase with the asymmetry of the waves.

  12. HYDRAULIC CHARACTERISTICS OF SEWER SEDIMENT GATE-FLUSHING TANKS: LABORATORY FLUME STUDIES

    EPA Science Inventory

    The objective of this study was to test the performance of gate-flushing tanks, simulated in a laboratory flume, to remove sediments from combined sewers and storage tanks. A significant amount of sediment/debris/sludge may accumulate at the bottom of a sewer during dry weather o...

  13. HYDRAULIC CHARACTERISTICS OF SEWER SEDIMENT GATE FLUSHING TANKS: LABORATORY FLUME STUDIES

    EPA Science Inventory

    The objective of this study was to test the performance of gate flushing tanks, simulated in a laboratory flume, to remove sediments from combined sewers and storage tanks. A significant amount of sediment/debris/sludge may accumulate at the bottom of a sewer during dry weather o...

  14. Progress in High-Level Waste Tank Cleaning at the Idaho National Environmental and Engineering Laboratory

    SciTech Connect

    Lockie, K. A.; McNaught, W. B.

    2002-02-26

    The Department of Energy Idaho Operations Office (DOE-ID) is making preparations to close two underground high-level waste (HLW) storage tanks at the Idaho National Engineering and Environmental Laboratory (INEEL) to meet Resource Conservation and Recovery Act (RCRA) regulations and Department of Energy (DOE) orders. Closure of these two tanks is scheduled for 2004 as the first phase in closure of the eleven 300,000 gallon tanks currently in service at the Idaho Nuclear Technology and Engineering Center (INTEC). Design, development, and deployment of a remotely operated tank cleaning system were completed in August 2001. The system incorporates many commercially available components, which have been adapted for application in cleaning high-level waste tanks. The system also uses existing waste transfer technology (steam-jets) to remove tank heel solids from the tank bottoms during the cleaning operations. By using this existing transfer system and commercially available equipment, the cost of developing custom designed cleaning equipment can be avoided. Remotely operated directional spray nozzles, automatic rotating wash balls, video monitoring equipment, decontamination spray-rings, and tank specific access interface devices have been integrated to provide a system that efficiently cleans tank walls and heel solids in an acidic, radioactive environment. This system is also compliant with operational and safety performance requirements at INTEC. Through the deployment of the tank cleaning system, the INEEL High Level Waste Program has demonstrated the capability to clean tanks to meet RCRA clean closure standards and DOE closure performance measures. The tank cleaning system deployed at the INTEC offers unique advantages over other approaches evaluated at the INEEL and throughout the DOE Complex. The system's ability to agitate and homogenize the tank heel sludge will simplify verification-sampling techniques and reduce the total quantity of samples required to

  15. Gas generation and retention in Tank 101-SY: A summary of laboratory studies, tank data, and information needs

    SciTech Connect

    Pederson, L.R.; Ashby, E.C.; Jonah, C.; Meisel, D.; Strachan, D.M.

    1992-06-01

    Chemical and radioactive wastes from processes used to separate plutonium from uranium are stored in underground tanks at the Hanford Site in Washington state. In March 1981, it was observed that the volume of wastes in Tank 101-SY slowly increased, followed by a rapid decrease and the venting of large quantities of gases. These cycles occurred every 8 to 15 weeks and continue to the present time. Subsequent analyses showed that these gases were composed primarily of hydrogen and nitrous oxide (N{sub 2}O). In response to the potential for explosion and release of hazardous materials to the environment, laboratory programs were initiated at Argonne National Laboratory (ANL), Georgia Institute of Technology (GIT), Pacific Northwest Laboratory (PNL), and Westinghouse Hanford Company (WHC), to develop a better understanding of the physical and chemical processes occurring in this waste tank. An aggressive sampling and analysis effort is also under way to characterize the wastes as fully as possible. These efforts will provide a technically defensible basis for safety analyses and future mitigation/remediation of the tank and its contents.

  16. A Laboratory Study Investigating the Feasibility of Applying Calcite-Type Coatings to Segregated Ballast Tanks

    DTIC Science & Technology

    1981-08-01

    A LABORATORY STUDY INVESTIGATIING THE FEASIBILITY OF APPLYING CALCITE -TYPE COATINGS TO SEGREGATED BALLAST TANKS AUGUST, 1981 Prepared by: Ocean City...Laboratory Study Investigating The Feasibility of Applying Calcite -Type Coatings to Segregated Ballast Tanks 5a. CONTRACT NUMBER 5b. GRANT NUMBER 5c...Executive Summary List of Figures I. Conclusions II. Introduction III. Background-The Development and Use of Calcite -Type Coatings IV. Experimental

  17. High level waste tank closure project: ALARA applications at the Idaho National Engineering and Environmental Laboratory.

    PubMed

    Aitken, Steven B; Butler, Richard; Butterworth, Steven W; Quigley, Keith D

    2005-05-01

    Bechtel BWXT Idaho, Maintenance and Operating Contractor for the Department of Energy at the Idaho National Engineering and Environmental Laboratory, has emptied, cleaned, and sampled six of the eleven 1.135 x 10(6) L high level waste underground storage tanks at the Idaho Nuclear Technology and Engineering Center, well ahead of the State of Idaho Consent Order cleaning schedule. Cleaning of a seventh tank is expected to be complete by the end of calendar year 2004. The tanks, with associated vaults, valve boxes, and distribution systems, are being closed to meet Resource Conservation and Recovery Act regulations and Department of Energy orders. The use of remotely operated equipment placed in the tanks through existing tank riser access points, sampling methods and application of as-low-as-reasonably-achievable (ALARA) principles have proven effective in keeping personnel dose low during equipment removal, tank, vault, and valve box cleaning, and sampling activities, currently at 0.03 Sv.

  18. FRACTIONAL CRYSTALLIZATION OF HANFORD SINGLE SHELL TANK (SST) WASTES LABORATORY DEVELOPMENT

    SciTech Connect

    HERTING, D.L.

    2006-12-05

    Laboratory studies demonstrate that fractional crystallization is a viable process for separating Hanford medium-curie waste into high-curie and low-curie fractions. The product salt from the crystallization process qualifies as low-curie feed to a supplemental treatment system (e.g., bulk vitrification). The high-curie raffinate is returned to the double-shell tank system, eventually to be sent as feed to the Waste Treatment and Immobilization Plant. Process flowsheet tests were designed with the aid of thermodynamic chemical modeling. Laboratory equipment design and test procedures were developed using simulated tank waste samples. Proof-of-concept flowsheet tests were carried out in a shielded hot cell using actual tank waste samples. Data from both simulated waste tests and actual tank waste tests demonstrate that the process exceeded all of the separation criteria established for the program.

  19. Characterization of low-level liquid wastes at the Oak Ridge National Laboratory

    SciTech Connect

    Peretz, F.J.; Clark, B.R.; Scott, C.B.; Berry, J.B.

    1986-12-01

    This report compiles and evaluates existing data on samples taken from the Oak Ridge National Laboratory Low-Level Liquid Waste (LLW) system. Although the primary focus is on the contents of the eight 50,000-gal Melton Valley Storage Tanks, data on raw LLW from the source facilities, Evaporator Service Tanks, and past operations involving the Gunite Storage Tanks are also included. A brief overview of the ORNL LLW system is provided. Methods of sample collection and analytical procedures are described. Data from each set of samples are reported and evaluated against criteria for classification of wastes. The quality and self-consistency of the data set are also discussed. Issues ranging from classifying as transuranic or Resource Conservation and Recovery Act hazardous waste to providing input for dose-rate calculations and evaluations of chemical compatibility with potential processing options are discussed. Remaining data voids are identified, and activities for filling those voids are recommended. 13 figs., 41 tabs.

  20. Melton Valley Storage Tanks Capacity Increase Project, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1995-04-01

    The US Department of Energy (DOE) proposes to construct and maintain additional storage capacity at Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee, for liquid low-level radioactive waste (LLLW). New capacity would be provided by a facility partitioned into six individual tank vaults containing one 100,000 gallon LLLW storage tank each. The storage tanks would be located within the existing Melton Valley Storage Tank (MVST) facility. This action would require the extension of a potable water line approximately one mile from the High Flux Isotope Reactor (HFIR) area to the proposed site to provide the necessary potable water for the facility including fire protection. Alternatives considered include no-action, cease generation, storage at other ORR storage facilities, source treatment, pretreatment, and storage at other DOE facilities.

  1. Safety evaluation for packaging 222-S laboratory cargo tank for onetime type B material shipment

    SciTech Connect

    Nguyen, P.M.

    1994-08-19

    The purpose of this Safety Evaluation for Packaging (SEP) is to evaluate and document the safety of the onetime shipment of bulk radioactive liquids in the 222-S Laboratory cargo tank (222-S cargo tank). The 222-S cargo tank is a US Department of Transportation (DOT) MC-312 specification (DOT 1989) cargo tank, vehicle registration number HO-64-04275, approved for low specific activity (LSA) shipments in accordance with the DOT Title 49, Code of Federal Regulations (CFR). In accordance with the US Department of Energy, Richland Operations Office (RL) Order 5480.1A, Chapter III (RL 1988), an equivalent degree of safety shall be provided for onsite shipments as would be afforded by the DOT shipping regulations for a radioactive material package. This document demonstrates that this packaging system meets the onsite transportation safety criteria for a onetime shipment of Type B contents.

  2. Design demonstrations for the remaining 19 Category B tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Not Available

    1993-06-01

    This document presents design demonstrations conducted of liquid low-level waste (LLLW) storage tank systems located at the Oak Ridge National Laboratory (ORNL). ORNL has conducted research in energy related fields since 1943. The facilities used to conduct the research include nuclear reactors, chemical pilot plants, research laboratories, radioisotope production laboratories, and support facilities. These facilities have produced a variety of radioactive and/or hazardous wastes that have been transported and stored through an extensive network of piping and tankage. Demonstration of the design of these tank systems has been stipulated by the Federal Facility Agreement (FFA) between the EPA (United States Environmental Protection Agency)-Region IV; the Tennessee Department of Environment and Conservation (TDEC); and the DOE. The FFA establishes four categories of tank systems: Category A-New or Replacement Tank Systems with Secondary Containment; Category B-Existing Tank Systems with Secondary Containment; Category C-Existing Tank Systems Without Secondary Containment, and Category D-Existing Tank Systems Without Secondary Containment That are Removed from Service. This document provides a design demonstration of the secondary containment and ancillary equipment of 19 tank systems listed in the FFA as Category B. The design demonstration for each tank is presented in Section 2. The assessments assume that each tank system was constructed in accordance with the design drawings and construction specifications for that system unless specified otherwise. Each design demonstration addresses system conformance to the requirements of the FFA (Appendix F, Section C).

  3. Design demonstrations for the remaining 19 Category B tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1995-01-01

    This document presents design demonstrations conducted of liquid low-level waste (LLLW) storage tank systems located at the Oak Ridge National Laboratory (ORNL). Demonstration of the design of these tank systems has been stipulated by the Federal Facility Agreement (FFA) between the US Environmental Protection Agency (EPA)--Region IV; the Tennessee Department of Environment and Conservation (TDEC); and the DOE. The FFA establishes four categories of tank systems: Category A--New or Replacement Tank Systems with Secondary Containment; Category B--Existing Tank Systems with Secondary Containment; Category C--Existing Tank Systems Without Secondary Containment; and Category D--Existing Tank Systems Without Secondary Containment That are Removed from Service. This document provides a design demonstration of the secondary containment and ancillary equipment of 19 tank systems listed in the FFA as Category B. Three tank systems originally designated as Category B have been redesignated as Category C and one tank system originally designated as Category B has been redesignated as Category D. The design demonstration for each tank is presented in Section 2. The design demonstrations were developed using information obtained from the design drawings (as-built when available), construction specifications, and interviews with facility operators. The assessments assume that each tank system was constructed in accordance with the design drawings and construction specifications for that system unless specified otherwise. Each design demonstration addresses system conformance to the requirements of the FFA.

  4. Intermediate-Scale Laboratory Experiments of Subsurface Flow and Transport Resulting from Tank Leaks

    SciTech Connect

    Oostrom, Martinus; Wietsma, Thomas W.

    2014-09-30

    Washington River Protection Solutions contracted with Pacific Northwest National Laboratory to conduct laboratory experiments and supporting numerical simulations to improve the understanding of water flow and contaminant transport in the subsurface between waste tanks and ancillary facilities at Waste Management Area C. The work scope included two separate sets of experiments: •Small flow cell experiments to investigate the occurrence of potential unstable fingering resulting from leaks and the limitations of the STOMP (Subsurface Transport Over Multiple Phases) simulator to predict flow patterns and solute transport behavior under these conditions. Unstable infiltration may, under certain conditions, create vertically elongated fingers potentially transporting contaminants rapidly through the unsaturated zone to groundwater. The types of leak that may create deeply penetrating fingers include slow release, long duration leaks in relatively permeable porous media. Such leaks may have occurred below waste tanks at the Hanford Site. •Large flow experiments to investigate the behavior of two types of tank leaks in a simple layered system mimicking the Waste Management Area C. The investigated leaks include a relatively large leak with a short duration from a tank and a long duration leak with a relatively small leakage rate from a cascade line.

  5. C-tank transfers: Transuranic sludge removal from the C-1, C-2, and W-23 waste storage tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Dahl, T.L.; Lay, A.C.; Taylor, S.A.; Moore, J.W.

    1999-05-01

    Two fluidic pulse jet mixing systems were used to successfully mobilize remote-handled transuranic sludge for retrieval from three 50,000-gal horizontal waste storage tanks at Oak Ridge National Laboratory (ORNL). The results of this operation indicate that the pulse jet system should be considered for mixing and bulk retrieval of sludges in other vertical and horizontal waste tanks at ORNL and at other U.S. Department of Energy sites.

  6. South Tank Farm underground storage tank inspection using the topographical mapping system for radiological and hazardous environments

    SciTech Connect

    Armstrong, G.A.; Burks, B.L.; Hoesen, S.D. van

    1997-07-01

    During the winter of 1997 the Topographical Mapping System (TMS) for hazardous and radiological environments and the Interactive Computer-Enhanced Remote-Viewing System (ICERVS) were used to perform wall inspections on underground storage tanks (USTs) W5 and W6 of the South Tank Farm (STF) at Oak Ridge National Laboratory (ORNL). The TMS was designed for deployment in the USTs at the Hanford Site. Because of its modular design, the TMS was also deployable in the USTs at ORNL. The USTs at ORNL were built in the 1940s and have been used to store radioactive waste during the past 50 years. The tanks are constructed with an inner layer of Gunite{trademark} that has been spalling, leaving sections of the inner wall exposed. Attempts to quantify the depths of the spalling with video inspection have proven unsuccessful. The TMS surface-mapping campaign in the STF was initiated to determine the depths of cracks, crevices, and/or holes in the tank walls and to identify possible structural instabilities in the tanks. The development of the TMS and the ICERVS was initiated by DOE for the purpose of characterization and remediation of USTs at DOE sites across the country. DOE required a three-dimensional, topographical mapping system suitable for use in hazardous and radiological environments. The intended application is mapping the interiors of USTs as part of DOE`s waste characterization and remediation efforts, to obtain both baseline data on the content of the storage tank interiors and changes in the tank contents and levels brought about by waste remediation steps. Initially targeted for deployment at the Hanford Site, the TMS has been designed to be a self-contained, compact, and reconfigurable system that is capable of providing rapid variable-resolution mapping information in poorly characterized workspaces with a minimum of operator intervention.

  7. FY 1999 cold demonstration of the Multi-Point Injection (MPI) process for stabilizing contaminated sludge in buried horizontal tanks with limited access at the Oak Ridge National Laboratory

    SciTech Connect

    Kauschinger, J.L.; Lewis, B.E.; Spence, R.D.

    2000-01-01

    A major problem faced by the U.S. Department of Energy is the remediation of buried tank waste. Exhumation of the sludge is currently the preferred remediation method. However, exhumation does not typically remove all the contaminated material from the tank. The best management practices for in-tank treatment of wastes require an integrated approach to develop appropriate treatment agents that can be safely delivered and uniformly mixed with the sludge. Ground Environmental Services, Inc., has developed and demonstrated a remotely controlled, high-velocity, jet-delivery system, which is termed Multi-Point-Injection (MPI{trademark}). This robust jet-delivery system has been used to create homogeneous monoliths containing shallow-buried miscellaneous waste in trenches [fiscal year (FY) 1995] and surrogate sludge in a cylindrical test tank (FY 1998). During the FY 1998 demonstration, the MPI process was able to successfully form a 32-ton uniform monolith in about 8 min. Analytical data indicated that 10 tons of a zeolite-type physical surrogate were uniformly mixed within the 40-inch-thick monolith without lifting the MPI jetting tools off the tank floor. Over 1,000 lb of cohesive surrogates, with consistencies of Gunite and Associated Tanks (GAATs) TH-4 and Hanford tank sludges, were easily mixed into the monolith without exceeding a core temperature of 100 F during curing.

  8. Houdini{trademark}: Reconfigurable in-tank mobile robot. Final report, June 1995--January 1997

    SciTech Connect

    Thompson, B.; Slifko, A.

    1998-12-31

    This report details the development of a reconfigurable in-tank robotic cleanup system called Houdini{trademark}. Driven by the general need to develop equipment for the removal of radioactive waste from hundreds of DOE waste storage tanks and the specific needs of DOE sites such as Oak Ridge National Laboratory and Fernald, Houdini{trademark} represents one of the possible tools that can be used to mobilize and retrieve this waste material for complete remediation. Houdini{trademark} is a hydraulically powered, track driven, mobile work vehicle with a collapsible frame designed to enter underground or above ground waste tanks through existing 24 inch riser openings. After the vehicle has entered the waste tank, it unfolds and lands on the waste surface or tank floor to become a remotely operated mini-bulldozer. Houdini{trademark} utilizes a vehicle mounted plow blade and 6-DOF manipulator to mobilize waste and carry other tooling such as sluicing pumps, excavation buckets, and hydraulic shears. The complete Houdini{trademark} system consists of the tracked vehicle and other support equipment (e.g., control console, deployment system, hydraulic power supply, and controller) necessary to deploy and remotely operate this system at any DOE site. Inside the storage tanks, the system is capable of performing heel removal, waste mobilization, waste size reduction, and other tank waste retrieval and decommissioning tasks. The first Houdini{trademark} system was delivered on September 24, 1996 to Oak Ridge National Laboratory (ORNL). The system acceptance test was successfully performed at a cold test facility at ORNL. After completion of the cold test program and the training of site personnel, ORNL will deploy the system for clean-up and remediation of the Gunite storage tanks.

  9. Estimates of laboratory accuracy and precision on Hanford waste tank samples

    SciTech Connect

    Dodd, D.A.

    1995-02-02

    A review was performed on three sets of analyses generated in Battelle, Pacific Northwest Laboratories and three sets generated by Westinghouse Hanford Company, 222-S Analytical Laboratory. Laboratory accuracy and precision was estimated by analyte and is reported in tables. The sources used to generate this estimate is of limited size but does include the physical forms, liquid and solid, which are representative of samples from tanks to be characterized. This estimate was published as an aid to programs developing data quality objectives in which specified limits are established. Data resulting from routine analyses of waste matrices can be expected to be bounded by the precision and accuracy estimates of the tables. These tables do not preclude or discourage direct negotiations between program and laboratory personnel while establishing bounding conditions. Programmatic requirements different than those listed may be reliably met on specific measurements and matrices. It should be recognized, however, that these are specific to waste tank matrices and may not be indicative of performance on samples from other sources.

  10. Underground radioactive waste tank remote inspection and sampling

    SciTech Connect

    Bzorgi, F.M.; Kelsey, A.P.; Van Hoesen, S.D.; Wiles, C.O.

    1996-04-01

    Characterization is a critical step in the remediation of contaminated materials and facilities. Severe physical- and radiological-access restrictions made the task of characterizing the World War II-era underground radioactive storage tanks at the Oak Ridge National Laboratory (ORNL) particularly challenging. The innovative and inexpensive tank characterization system (TCS) developed to meet this challenge at ORNL is worthy of consideration for use in similar remediation projects. The TCS is a floating system that uses the existing water in the tank as a platform that supports instruments and samplers mounted on a floating boom. TCS operators feed the unit into an existing port of the tank to be characterized. Once inserted, the system`s position is controlled by rotation and by insertion and withdrawal of the boom. The major components of the TCS system include the following: (1) boom support system that consists of a boom support structure and a floating boom, (2) video camera and lights, (3) sludge grab sampler, (4) wall chip sampler, and (5) sonar depth finder. This simple design allows access to all parts of a tank. Moreover, the use of off-the-shelf components keeps the system inexpensive and minimizes maintenance costs. The TCS proved invaluable in negotiating the hazards of ORNL`s Gunite and Associated Tanks, which typically contain a layer of radioactive sludge, have only one to three access ports that are usually only 12- or 24-in. in diameter, and range from 12 to 50 ft in diameter. This paper reviews both the successes and the difficulties encountered in using the TCS for treatability studies at ORNL and discusses the prospects for its wider application in remediation activities.

  11. Contingency plan for the Old Hydrofracture Facility Tanks Sluicing Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1998-06-01

    This revised contingency plan addresses potential scenarios involving the release of radioactively contaminated waste from the Old Hydrofracture Facility Tanks Contents Removal project to the environment. The tanks are located at the Oak Ridge National Laboratory. The project involves sluicing the contents of the five underground tanks to mix the sludge and supernatant layers, and pumping the mixture to the Melton Valley Storage Tanks (MVST) for future processing. The sluicing system to be used for the project consists of a spray nozzle designated the {open_quotes}Borehole Miner,{close_quotes} with an associated pump; in-tank submersible pumps to transfer tank contents from the sluice tanks to the recycle tank; high-pressure pumps providing slurry circulation and slurry transport to the MVST; piping; a ventilation system; a process water system; an instrumentation and control system centered around a programmable logic controller; a video monitoring system; and auxiliary equipment. The earlier version of this plan, which was developed during the preliminary design phase of the project, identified eight scenarios in which waste from the tanks might be released to the environment as a result of unanticipated equipment failure or an accident (e.g., vehicular accident). One of those scenarios, nuclear criticality, is no longer addressed by this plan because the tank waste will be isotopically diluted before sluicing begins. The other seven scenarios have been combined into three, and a fourth, Borehole Miner Failure, has been added as follows: (1) underground release from the tanks; (2) aboveground release or spill from the sluicing system, a tank riser, or the transfer pipeline; (3) release of unfiltered air through the ventilation system; and (4) Borehole Miner arm retraction failure. Methods for preventing, detecting, and responding to each release scenario are set out in the plan.

  12. High-Frequency, Crosswell Radar Data Collected in a Laboratory Tank

    USGS Publications Warehouse

    Peters, Bas; Moulton, Craig W.; Ellefsen, Karl J.; Horton, Robert J.; McKenna, Jason R.

    2010-01-01

    Crosswell radar data were collected among three wells in a laboratory tank filled with dry sand. Embedded within the sand was a long plastic box, which was the target for the data collection. Two datasets were collected between each pair of wells, making a total of six datasets. The frequencies in the data ranged from 0.5 to 1.5 gigahertz, and the peak frequency was 0.9 gigahertz. The data are well suited for evaluating various processing algorithms, and the data linearly scale to typical field conditions.

  13. The effect of impeller type on silica sol formation in laboratory scale agitated tank

    NASA Astrophysics Data System (ADS)

    Nurtono, Tantular; Suprana, Yayang Ade; Latif, Abdul; Dewa, Restu Mulya; Machmudah, Siti; Widiyastuti, Winardi, Sugeng

    2016-02-01

    The multiphase polymerization reaction of the silica sol formation produced from silicic acid and potassium hydroxide solutions in laboratory scale agitated tank was studied. The reactor is equipped with four segmental baffle and top entering impeller. The inside diameter of reactor is 9 cm, the baffle width is 0.9 cm, and the impeller position is 3 cm from tank bottom. The diameter of standard six blades Rushton and three blades marine propeller impellers are 5 cm. The silicic acid solution was made from 0.2 volume fraction of water glass (sodium silicate) solution in which the sodium ion was exchanged by hydrogen ion from cation resin. The reactor initially filled with 286 ml silicic acid solution was operated in semi batch mode and the temperature was kept constant in 60 °C. The 3 ml/minute of 1 M potassium hydroxide solution was added into stirred tank and the solution was stirred. The impeller rotational speed was varied from 100 until 700 rpm. This titration was stopped if the solution in stirred tank had reached the pH of 10-The morphology of the silica particles in the silica sol product was analyzed by Scanning Electron Microscope (SEM). The size of silica particles in silica sol was measured based on the SEM image. The silica particle obtained in this research was amorphous particle and the shape was roughly cylinder. The flow field generated by different impeller gave significant effect on particle size and shape. The smallest geometric mean of length and diameter of particle (4.92 µm and 2.42 µm, respectively) was generated in reactor with marine propeller at 600 rpm. The reactor with Rushton impeller produced particle which the geometric mean of length and diameter of particle was 4.85 µm and 2.36 µm, respectively, at 150 rpm.

  14. Oak Ridge National Laboratory Old Hydrofracture Facility Tank Closure Plan and Grout Development Status Report for FY 1999

    SciTech Connect

    Lewis, B.E.

    2000-05-08

    U.S. Department of Energy (DOE) facilities across the country have radioactive waste underground storage tanks, which will require either complete removal of the tank contents and tank shells or in-place stabilization of sludge heels. Complete removal of the sludge and tank shells can become costly while providing little benefit to health, safety, and the environment. An alternative to the removal of the residual wastes and tank shells is the use of in situ solidification and stabilization techniques to immobilize the Resource Conservation and Recovery Act (RCRA) and radioactive components present in waste storage tanks. One technology for in situ remediation of tank wastes is Ground Environmental Service's (GES's) Multi-Point-Injection (MPI.) technology. MPI technology is a patented delivery system, which uses simple and inexpensive injection tools for rapid delivery of grout or other treatment agents, as well as for the emplacement of subsurface barriers. Through the use of tailored grout formulations in conjunction with a system of specially designed grout injection tools, MPI technology is capable of producing a uniform mixture of sludge and grout. Grouts can be tailored for the immobilization of specific RCRA and radioactive constituents. The system of injection tools is designed to maximize the mixing efficiency of the grout with the wastes in the tank. MPI technology has been successfully demonstrated on the solidification of shallow buried wastes at the Oak Ridge Y-12 Plant and in large-scale pumping and mixing tests in both cylindrical and horizontal simulated waste tanks. Hot demonstration of the technology will be accomplished during the closure of the Old Hydrofracture Facility (OHF) tank at the Oak Ridge National Laboratory (ORNL) in fiscal year 2000. This report describes the closure plan for the OHF tanks and presents the status of grout formulation development at ORNL.

  15. Contingency plan for the Old Hydrofracture Facility tanks sluicing project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1996-10-01

    Lockheed Martin Energy Systems, Inc. (Energy Systems), plans to begin a sluicing (flushing) and pumping project to remove the contents from five inactive, underground storage tanks at the Old Hydrofracture Facility (OHF) at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The tank contents will be transferred to the Melton Valley Storage Tanks, which are part of the active waste treatment system at ORNL. The purpose of the project is to minimize the risk of leaking the highly radioactive material to the environment. The five OHF tanks each contain a layer of sludge and a layer of supernatant. Based on a sampling project undertaken in 1995, the sludge in the tanks has been characterized as transuranic and mixed waste and the supernatants have been characterized as mixed waste. The combined radioactivity of the contents of the five tanks is approximately 29,500 Ci. This contingency plan is based on the preliminary design for the project and describes a series of potential accident/release scenarios for the project. It outlines Energy Systems` preliminary plans for prevention, detection, and mitigation. Prevention/detection methods range from using doubly contained pipelines to alarmed sensors and automatic pump cutoff systems. Plans for mitigation range from pumping leaked fluids from the built-in tank drainage systems and cleaning up spilled liquids to personnel evacuation.

  16. Integration of Environmental Restoration and Waste Management Activities for a More Cost-Effective Tank Remediation Program Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Brill, A.; Clark, R.; Stewart, R.

    1998-06-01

    This paper presents plans and strategies for remediation of the liquid low-level radioactive waste (LLLW) tanks that have been removed from service (also known as inactive tanks) at Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee. Much of the LLLW system at ORNL was installed more than 50 years ago. The overall objective of the Inactive Tank Program is to remediate all LLLW tanks that have been removed from service to the extent practicable in accordance with the regulatory requirements.

  17. The effect of impeller type on silica sol formation in laboratory scale agitated tank

    SciTech Connect

    Nurtono, Tantular; Suprana, Yayang Ade; Latif, Abdul; Dewa, Restu Mulya; Machmudah, Siti; Widiyastuti, Winardi, Sugeng

    2016-02-08

    The multiphase polymerization reaction of the silica sol formation produced from silicic acid and potassium hydroxide solutions in laboratory scale agitated tank was studied. The reactor is equipped with four segmental baffle and top entering impeller. The inside diameter of reactor is 9 cm, the baffle width is 0.9 cm, and the impeller position is 3 cm from tank bottom. The diameter of standard six blades Rushton and three blades marine propeller impellers are 5 cm. The silicic acid solution was made from 0.2 volume fraction of water glass (sodium silicate) solution in which the sodium ion was exchanged by hydrogen ion from cation resin. The reactor initially filled with 286 ml silicic acid solution was operated in semi batch mode and the temperature was kept constant in 60 °C. The 3 ml/minute of 1 M potassium hydroxide solution was added into stirred tank and the solution was stirred. The impeller rotational speed was varied from 100 until 700 rpm. This titration was stopped if the solution in stirred tank had reached the pH of 10-The morphology of the silica particles in the silica sol product was analyzed by Scanning Electron Microscope (SEM). The size of silica particles in silica sol was measured based on the SEM image. The silica particle obtained in this research was amorphous particle and the shape was roughly cylinder. The flow field generated by different impeller gave significant effect on particle size and shape. The smallest geometric mean of length and diameter of particle (4.92 µm and 2.42 µm, respectively) was generated in reactor with marine propeller at 600 rpm. The reactor with Rushton impeller produced particle which the geometric mean of length and diameter of particle was 4.85 µm and 2.36 µm, respectively, at 150 rpm.

  18. Laboratory tank studies of a single species of phytoplankton using a remote sensing fluorosensor

    NASA Technical Reports Server (NTRS)

    Brown, C. A., Jr.; Jarrett, O., Jr.; Farmer, F. H.

    1981-01-01

    Phytoplankton were grown in the laboratory for the purpose of testing a remote fluorosensor. The fluorosensor uses a unique four-wavelength dye laser system to excite phytoplankton bearing chlorophyll and to measure the chlorophyll fluorescence generated by this excitation. Six different species were tested, one at a time, and each was grown two to four times. Fluorescence measured by the fluorosensor provides good quantitative measurement of chlorophyll concentrations for all species tested while the cultures were in log phase growth. Fluorescene cross section ratios obtained in the single species tank tests support the hypothesis that the shape of the fluorescence cross section curve remains constant with the species (differences in fluorescence cross section ratios are a basis for determining composition of phytoplankton according to color group when a multiwavelength source of excitation is used. Linear relationships exist between extracted chlorophyll concentration and fluorescence measured by the remote fluorosensor during the log phase growth of phytoplankton cultures tested.

  19. Laboratory Class Project: Using a Cichlid Fish Display Tank to Teach Students about Complex Behavioral Systems.

    PubMed

    Nolan, Brian C

    2010-01-01

    Laboratory activities serve several important functions in undergraduate science education. For neuroscience majors, an important and sometimes underemphasized tool is the use of behavioral observations to help inform us about the consequences of changes that are occurring on a neuronal level. To help address this concern, the following laboratory exercise is presented. The current project tested the prediction that the most dominant fish in a tank of cichlids will have gained the most benefits of its position resulting in the greatest growth and hence, become the largest fish. More specifically: (1) is there evidence that a social hierarchy exists among the fish in our tank based on the number of aggressive acts among the four largest fish; (2) if so, does the apparent rank correspond to the size of the fish as predicted by previous studies? Focal sampling and behavior sampling of aggressive acts between fish were utilized in the data collection. Collectively, the data suggest a social dominance hierarchy may be in place with the following rank order from highest to lowest: Fish A > Fish B > Fish D > Fish C. While the largest (Fish A) seems to be at the top, Fish C ended up being ranked lower than Fish D despite the fact that Fish C is larger. Overall, the project was considered a success by the instructor and students. The students offered several suggestions that could improve future versions of this type of project, in particular concerning the process of constructing a poster about the project. The implications of the data and student learning outcomes are discussed.

  20. Cold test plan for the Old Hydrofracture Facility tank contents removal project, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1997-11-01

    This Old Hydrofracture Facility (OHF) Tanks Contents Removal Project Cold Test Plan describes the activities to be conducted during the cold test of the OHF sluicing and pumping system at the Tank Technology Cold Test Facility (TTCTF). The TTCTF is located at the Robotics and Process Systems Complex at the Oak Ridge National Laboratory (ORNL). The cold test will demonstrate performance of the pumping and sluicing system, fine-tune operating instructions, and train the personnel in the actual work to be performed. After completion of the cold test a Technical Memorandum will be prepared documenting completion of the cold test, and the equipment will be relocated to the OHF site.

  1. Risk characterization data manual for Category D inactive liquid low-level waste tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Not Available

    1993-09-01

    This manual reports the results of a risk characterization of Category D inactive liquid low-level radioactive waste (LLLW) underground storage tanks (Uses) at the Oak Ridge National Laboratory (ORNL). The risk characterization is required by the Federal Facility Agreement between the Department of Energy-Oak Ridge Operations Office, the Environmental Protection Agency-Region IV, and the Tennessee Department of Environment and Conservation. The intent of the risk characterization is to determine relative priorities for assessment and remediation. A total of 55 FFA Category D inactive LLLW tanks are discussed in this manual. Of the 39 tanks at ORNL that have been accepted into the Environmental Restoration (ER) Program, all have been sampled for preliminary characterization, except for 5 tanks that were found to be empty plus I that was found not to exist. The remaining 16 tanks are in the Waste Management (WM) Program. Twelve were sampled for preliminary characterization, and four were found empty. Each sampled tank was scored on a scale of I to 5 on the basis of three criteria: (1) leak characteristics, (2) location, and (3) toxicological characteristics of residual sludges and liquids. Each criterion was assigned a weighing factor based on perceived importance. The criterion score multiplied by the weighting factor equaled the tank`s total score for that criterion. The three weighted criterion scores for each tank were then summed for a total score for that tank. When the scores for all tanks had been weighted and summed, the tanks were ranked in descending order on the basis of their total scores. The highest possible score for a tank is 30. The descending rank order represents the recommended priorities for evaluation: the higher the score, the higher the priority for evaluation. Of the 54 tanks sampled in the risk characterization, 23 tanks scored 16 or higher, 11 scored between 10 and 15, 5 scored between 4 and 9, and 15 scored 3 or less.

  2. Action memorandum for the Waste Area Grouping 1 Tank WC-14 removal action at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1994-11-01

    This action memorandum documents approval for a Comprehensive Environmental Response, Compensation, and Liability Act of 1980, as amended (CERCLA), time-critical action. The action will remove radiologically contaminated water from Tank WC-14. The water contains a polychlorinated biphenyl (PCB) at a level below regulatory concern. Tank WC-14 is located in the Waste Area Grouping (WAG) 1 WC-10 Tank Farm at the Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee. Contaminated sludge remaining in the tank after removal of the liquid will be the subject of a future action.

  3. Cold Testing of a Russian Pulsating Mixer Pump at the Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Lewis, BE

    2002-01-29

    Russian pulsating mixer pump (PMP) technology was identified in FY 1996 during technical exchanges between the U.S. Department of Energy (DOE) Tanks Focus Area Retrieval and Closure program, the DOE Environmental Management International Programs, and delegates from Russia as a technology that could be implemented in tank waste retrieval operations in the United States. The PMP is basically a jet mixer powered by a pressure/vacuum supply system. A prototype PMP was provided by the Russian Mining and Chemical Combine and evaluated as a potential retrieval tool in FY 1997 at Pacific Northwest National Laboratory (PNNL). Based on this evaluation, Oak Ridge National Laboratory (ORNL) and DOE staff determined that a modified PMP would meet project needs for bulk mobilization of sludge from one or more of the Gunite and Associated Tanks (GAAT) at ORNL. In FY 1998, PMP technology was selected for deployment in one of the GAAT to mobilize settled solids. Deployment of the PMP was expected to reduce operation and maintenance costs required to utilize more expensive retrieval systems. The following series of cold tests and inspections were conducted on one of the three PMP units provided to verify the acceptability and readiness of the mixing system for operation in the GAATs at ORNL: (1) Inspections and measurements designed to evaluate the integrity of the equipment: Fabrication shop inspections, Equipment inspections, Vibration/oscillation measurements, Hydrostatic pressure tests. (2) Functionality of the system components: Tank riser interface functionality, Decontamination spray ring (DSR) functionality, Valves, actuator, sensors, and control system functionality, Support fixture tests; and Contamination control assessment. (3) Mixing and operational performance of the PMP system: DSR performance, PMP debris tolerance, PMP performance with water only, PMP cleaning radius determination, and PMP performance with sludge surrogates. The results from these tests indicate

  4. Alternatives evaluation and decommissioning study on shielded transfer tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    DeVore, J.R.; Hinton, R.R.

    1994-08-01

    The shielded transfer tanks (STTs) are five obsolete cylindrical shipping casks which were used to transport high specific activity radioactive solutions by rail during the 1960s and early 1970s. The STTs are currently stored at the Oak Ridge National Laboratory under a shed roof. This report is an evaluation to determine the preferred alternative for the final disposition of the five STTs. The decommissioning alternatives assessed include: (1) the no action alternative to leave the STTs in their present location with continued surveillance and maintenance; (2) solidification of contents within the tanks and holding the STTs in long term retrievable storage; (3) sale of one or more of the used STTs to private industry for use at their treatment facility with the remaining STTs processed as in Alternative 4; and (4) removal of tank contents for de-watering/retrievable storage, limited decontamination to meet acceptance criteria, smelting the STTs to recycle the metal through the DOE contaminated scrap metal program, and returning the shielding lead to the ORNL lead recovery program because the smelting contractor cannot reprocess the lead. To completely evaluate the alternatives for the disposition of the STTs, the contents of the tanks must be characterized. Shielding and handling requirements, risk considerations, and waste acceptance criteria all require that the radioactive inventory and free liquids residual in the STTs be known. Because characterization of the STT contents in the field was not input into a computer model to predict the probable inventory and amount of free liquid. The four alternatives considered were subjected to a numerical scoring procedure. Alternative 4, smelting the STTs to recycle the metal after removal/de-watering of the tank contents, had the highest score and is, therefore, recommended as the preferred alternative. However, if a buyer for one or more STT could be found, it is recommended that Alternative 3 be reconsidered.

  5. LABORATORY TESTING TO SIMULATE VAPOR SPACE CORROSION IN RADIOACTIVE WASTE STORAGE TANKS

    SciTech Connect

    Wiersma, B.; Garcia-Diaz, B.; Gray, J.

    2013-08-30

    Radioactive liquid waste has been stored in underground carbon steel tanks for nearly 70 years at the Hanford nuclear facility. Vapor space corrosion of the tank walls has emerged as an ongoing challenge to overcome in maintaining the structural integrity of these tanks. The interaction between corrosive and inhibitor species in condensates/supernates on the tank wall above the liquid level, and their interaction with vapor phase constituents as the liquid evaporates from the tank wall influences the formation of corrosion products and the corrosion of the carbon steel. An effort is underway to gain an understanding of the mechanism of vapor space corrosion. Localized corrosion, in the form of pitting, is of particular interest in the vapor space. CPP testing was utilized to determine the susceptibility of the steel in a simulated vapor space environment. The tests also investigated the impact of ammonia gas in the vapor space area on the corrosion of the steel. Vapor space coupon tests were also performed to investigate the evolution of the corrosion products during longer term exposures. These tests were also conducted at vapor space ammonia levels of 50 and 550 ppm NH{sub 3} (0.005, and 0.055 vol.%) in air. Ammonia was shown to mitigate vapor space corrosion.

  6. Waste Characterization Data Manual for the inactive liquid low-level waste tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

    SciTech Connect

    Not Available

    1993-06-01

    This Waste Characterization Data Manual contains the results of an analysis of the contents of liquid low-level waste (LLLW) tanks that have been removed from service in accordance with the requirements of the Oak Ridge National Laboratory (ORNL) Federal Facility Agreement (FFA), Section IX.G.1. Section IX.G.1 of the FFA requires waste characterizations be conducted and provided to EPA and TDEC for all LLLW tanks that are removed from service. These waste characterizations shall include the results of sampling and analysis of the tank contents, including wastes, liquids, and sludges. This manual was first issued as ORNL/ER-80 in June 1992. The waste characterization data were extracted from ORNL reports that described tank sampling and analysis conducted in 1988 for 32 out-of-service tanks. This revision of the manual contains waste characterization data for 54 tanks, including the 32 tanks from the 1988 sampling campaign (Sects. 2.1 through 2.32) and the 22 additional tanks from a subsequent sampling campaign in 1992 and 1993 (Sects. 2.33 through 2.54). Data are presented from analyses of volatile organic compounds, semivolatile organic compounds, polychlorinated biphenyls (PCBs), pesticides, radiochemical compounds, and inorganic compounds. As additional data resulting from analyses of out-of-service tank samples become available, they will be added to this manual.

  7. Risk characterization data manual for inactive liquid low-level waste tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Not Available

    1992-09-01

    This manual reports the results of a risk characterization of inactive liquid low-level radioactive waste (LLLW) underground storage tanks (USTs) at the Oak Ridge National Laboratory (ORNL). Of the 39 tanks at ORNL that have been accepted into the Environmental Restoration Program, the 29 LLLW USTs that have been sampled for preliminary characterization were considered. Each tank was scored on a scale of 1 to 5 on the basis of three criteria: (1) leak characteristics, (2) location, and (3) toxicological characteristics of residual sludges and liquids. Each criterion was then weighted according to perceived importance. The criterion score multiplied by the weighting factor equaled the tank's total score for that criterion. The three weighted criterion scores for each tank were then summed for a total score for that tank. When the scores for all tanks had been weighted and summed, the tanks were ranked in descending order on the basis of their total scores. The highest possible score for a tank is 30. The descending rank order represents the recommended priorities for evaluation: the higher the score, the higher the priority for evaluation.

  8. Exploration of a Buried Building Foundation and a Septic Tank Plume Dispersion Using a Laboratory-fabricated Resistivity Apparatus

    NASA Astrophysics Data System (ADS)

    Lachhab, A.; Stepanik, N.; Booterbaugh, A.

    2010-12-01

    In the following study, an electrical resistivity device was built and used in both a laboratory setup and in the field to accurately identify the location of a septic tank and the foundation of Gustavus Adolphus (GA); a building that was burned at Susquehanna University in 1964. The entire apparatus, which costs a fraction of the price of a typical electrical resistivity device, was tested for accuracy in the laboratory prior to its use in the field. The electrical resistivity apparatus consists of a deep-cycle twelve volt battery, an AC to DC inverter and two multimeters to measure the potential and the current intensity from four linear electrodes via a wireless data transmission system. This apparatus was constructed by using basic inexpensive electrical and electronic equipments. The recorded potential and current values were used to calculate the apparent resistivity of different materials adopting the Wenner array for both investigations. Several tests were performed on the tabletop bench, producing consistent results when applied to find small bricks structures with different geometrical arrangement buried under a mixed sand-soil formation. The apparatus was also used to investigate a subsurface salty water plume in the same formation. The horizontal resistivity profile obtained over the vertical small brick wall matched the theoretical apparent resistivity of resistivity versus displacement on a vertical dike in a homogeneous material. In addition, the two-dimensional resistivity profile replicate the salty plume size conformably. Following the success on the small-scale laboratory tabletop bench, the electrical resistivity apparatus was implemented in the field to explore the foundation of GA in one location and the septic tank in another. An array of transects were performed, analyzed and plotted using MATLAB. The three dimensional contours of apparent resistivity depicted exactly the locations of the buried foundation walls, the septic tank and the

  9. Design demonstrations for Category B tank systems piping at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1994-12-01

    Demonstration of the design of the piping systems described in this report is stipulated by the Federal Facility Agreement (FFA) between the U.S. Environmental Protection Agency (EPA)-Region IV, the Tennessee Department of Environment and Conservation (TDEC), and the U.S. Department of Energy (DOE). This report provides a design demonstration of the secondary containment and ancillary equipment of 30 piping systems designated in the FFA as Category B (i.e., existing tank systems with secondary containment). Based on the findings of the Design Demonstrations for the Remaining 19 Category B Tank Systems, (DOE/OR/03-1150 & D2), three tank systems originally designated as Category B have been redesignated as Category C (i.e., existing tank systems without secondary containment). The design demonstrations were developed using information obtained from design drawings (as-built when available), construction specifications, and interviews with facility operators. Each design demonstration addresses system conformance to the requirements of the FFA (Appendix F, Section C). Deficiencies or restrictions regarding the ability to demonstrate that each of the containment systems conforms to FFA requirements are noted in the discussion of each piping system and presented in Table 2.0-1.

  10. FRACTIONAL CRYSTALLIZATION LABORATORY TESTING FOR INCLUSION & COPRECIPITATION WITH ACTUAL TANK WASTE

    SciTech Connect

    WARRANT, R.W.

    2006-12-11

    Fractional crystallization is being considered as a pretreatment method to support supplemental treatment of retrieved single-shell tank (SST) saltcake waste at the Hanford Site. The goal of the fractional crystallization process is to optimize the separation of the radioactivity (radionuclides) from the saltcake waste and send it to the Waste Treatment and Immobilization Plant and send the bulk of the saltcake to the supplemental treatment plant (bulk vitrification). The primary factors that influence the separation efficiency are (1) solid/liquid separation efficiency, (2) contaminant inclusions, and (3) co-precipitation. This is a report of testing for factors (2) and (3) with actual tank waste samples. For the purposes of this report, contaminant inclusions are defined as the inclusion of supernatant, containing contaminating radionuclides, in a pocket within the precipitating saltcake crystals. Co-precipitation is defined as the simultaneous precipitation of a saltcake crystal with a contaminating radionuclide. These two factors were tested for various potential fractional crystallization product salts by spiking the composite tank waste samples (SST Early or SST Late, external letter CH2M-0600248, ''Preparation of Composite Tank Waste Samples for ME-21 Project'') with the desired target salt and then evaporating to precipitate that salt. SST Early represents the typical composition of dissolved saltcake early in the retrieval process, and SST Late represents the typical composition during the later stages of retrieval.

  11. Summary review of the chemical characterization of liquid and sludge contained in the Old Hydrofracture tanks, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Francis, C.W.; Herbes, S.E.

    1997-02-01

    This report presents analytical data developed from samples collected from the five inactive tanks located at the Old Hydrofracture Facility (OHF) at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The samples were collected during December 1995 and January 1996. The purpose of the sampling and analysis project was (1) to determine whether the tank contents meet ORNL waste acceptance criteria, as specified in the Oak Ridge National Laboratory, Liquid Waste Treatment Systems, Waste Evaluation Criteria; (2) to determine various physical properties of the tank contents that would affect the design of a sludge mobilization system; and (3) to gather information to support a baseline risk assessment. The report focuses on the analytical results used to evaluate the tank contents with regard to nuclear criticality safety requirements and to regulatory waste characterization.

  12. Laboratory Demonstration of the Pretreatment Process with Caustic and Oxidative Leaching Using Actual Hanford Tank Waste

    SciTech Connect

    Fiskum, Sandra K.; Billing, Justin M.; Buck, Edgar C.; Daniel, Richard C.; Draper, Kathryn E.; Edwards, Matthew K.; Jenson, Evan D.; Kozelisky, Anne E.; MacFarlan, Paul J.; Peterson, Reid A.; Shimskey, Rick W.; Snow, Lanee A.

    2009-01-01

    This report describes the bench-scale pretreatment processing of actual tank waste materials through the entire baseline WTP pretreatment flowsheet in an effort to demonstrate the efficacy of the defined leaching processes on actual Hanford tank waste sludge and the potential impacts on downstream pretreatment processing. The test material was a combination of reduction oxidation (REDOX) tank waste composited materials containing aluminum primarily in the form of boehmite and dissolved S saltcake containing Cr(III)-rich entrained solids. The pretreatment processing steps tested included • caustic leaching for Al removal • solids crossflow filtration through the cell unit filter (CUF) • stepwise solids washing using decreasing concentrations of sodium hydroxide with filtration through the CUF • oxidative leaching using sodium permanganate for removing Cr • solids filtration with the CUF • follow-on solids washing and filtration through the CUF • ion exchange processing for Cs removal • evaporation processing of waste stream recycle for volume reduction • combination of the evaporated product with dissolved saltcake. The effectiveness of each process step was evaluated by following the mass balance of key components (such as Al, B, Cd, Cr, Pu, Ni, Mn, and Fe), demonstrating component (Al, Cr, Cs) removal, demonstrating filterability by evaluating filter flux rates under various processing conditions (transmembrane pressure, crossflow velocities, wt% undissolved solids, and PSD) and filter fouling, and identifying potential issues for WTP. The filterability was reported separately (Shimskey et al. 2008) and is not repeated herein.

  13. Laboratory testing of ozone oxidation of Hanford Site waste from Tank 241-SY-101

    SciTech Connect

    Delegard, C.H.; Stubbs, A.M.; Bolling, S.D.

    1993-12-14

    Ozone was investigated as a reagent to oxidize and destroy organic species present in simulated and genuine waste from Hanford Site Tank 241-SY-101 (Tank 101-SY). Two high-shear mixing apparatus were tested to perform the gas-to-solution mass transfer necessary to achieve efficient use of the ozone reagent. Oxidations of nitrite (to form nitrate) and organic species were observed. The organics oxidized to form carbonate and oxalate as well as nitrate and nitrogen gas from nitrogen associated with the organic. oxidations of metal species also were observed directly or inferred by solubilities. The chemical reaction stoichiometries were consistent with reduction of one oxygen atom per ozone molecule. Acetate, oxalate, and formate were found to comprise about 40% of the genuine waste`s total organic carbon (TOC) concentration. Ozonation was found to be chemically feasible for destroying organic species (except oxalate) present in the wastes in Tank 101-SY. The simulated waste formulation used in these studies credibly modelled the ozonation behavior of the genuine waste.

  14. 1997 structural integrity assessments for the Category C liquid low-level waste tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1997-09-01

    This report presents the results of a series of evaluations to determine if the individual Category C tank systems retain sufficient structural integrity to continue being used for liquid storage. The approach used to reach the final certification/conclusion consisted of three phases, including: (1) Review of the original engineering design drawings and construction materials to determine whether the tank and line systems were capable of containing liquids without leaking (and also to check that the construction materials were compatible with liquids that might have been placed in these systems). While drawings in this report may be of poor quality, they are copies of the best available originals. (2) A qualitative corrosion assessment conducted in 1995 that further evaluated both the potential internal corrosion effects of materials in the tank and in the potential external corrosion effects of the backfill and native soil at the Oak Ridge National Laboratory (ORNL). The ability to accurately measure or predict the amount of corrosion present on both the internal and external walls of the tanks and pipelines is extremely limited. However, when available, data were used to assess the historical tank contents and usage and the probable corrosive effects on the tank system materials of construction. (3) Performance of monthly leak tests were completed on the tanks and annual leak tests were completed on associated testable pipelines. This task was judged to be the most important criteria for determining structural integrity due to the proven performance of the technology and processes involved.

  15. Risk-based prioritization for the interim remediation of inactive low-level liquid radioactive waste underground storage tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Chidambariah, V.; Travis, C.C.; Trabalka, J.R.; Thomas, J.K.

    1992-09-01

    The paper presents a risk-based approach for rapid prioritization of low-level liquid radioactive waste underground storage tanks (LLLW USTs), for possible interim corrective measures and/or ultimate closure. The ranking of LLLW USTs is needed to ensure that tanks with the greatest potential for adverse impact on the environment and human health receive top priority for further evaluation and remediation. Wastes from the LLLW USTs at Oak Ridge National Laboratory were pumped out when the tanks were removed from service. The residual liquids and sludge contain a mixture of radionuclides and chemicals. Contaminants of concern that were identified in the liquid phase of the inactive LLLW USTs include the radionuclides [sup 90]Sr, [sup 137]Cs, and [sup 233]U and the chemicals carbon tetrachloride, trichloroethane, tetrachloroethene, methyl ethyl ketone, mercury, lead, and chromium. The risk-based approach for prioritization of the LLLW USTs is based upon three major criteria: (1) leaking characteristics of the tank, (2) location of the tanks, and (3) toxic potential of the tank contents. Leaking characteristics of LLLW USTs will aid in establishing the potential for the release of contaminants to environmental media. In this study, only the liquid phase was assumed to be released to the environment. Scoring criteria for release potential of LLLW USTs was determined after consideration of the magnitude of any known leaks and the tank type for those that are not known to leak.

  16. Risk-based prioritization for the interim remediation of inactive low-level liquid radioactive waste underground storage tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Chidambariah, V.; Travis, C.C.; Trabalka, J.R.; Thomas, J.K.

    1992-09-01

    The paper presents a risk-based approach for rapid prioritization of low-level liquid radioactive waste underground storage tanks (LLLW USTs), for possible interim corrective measures and/or ultimate closure. The ranking of LLLW USTs is needed to ensure that tanks with the greatest potential for adverse impact on the environment and human health receive top priority for further evaluation and remediation. Wastes from the LLLW USTs at Oak Ridge National Laboratory were pumped out when the tanks were removed from service. The residual liquids and sludge contain a mixture of radionuclides and chemicals. Contaminants of concern that were identified in the liquid phase of the inactive LLLW USTs include the radionuclides {sup 90}Sr, {sup 137}Cs, and {sup 233}U and the chemicals carbon tetrachloride, trichloroethane, tetrachloroethene, methyl ethyl ketone, mercury, lead, and chromium. The risk-based approach for prioritization of the LLLW USTs is based upon three major criteria: (1) leaking characteristics of the tank, (2) location of the tanks, and (3) toxic potential of the tank contents. Leaking characteristics of LLLW USTs will aid in establishing the potential for the release of contaminants to environmental media. In this study, only the liquid phase was assumed to be released to the environment. Scoring criteria for release potential of LLLW USTs was determined after consideration of the magnitude of any known leaks and the tank type for those that are not known to leak.

  17. Glass Waste Forms for Oak Ridge Tank Wastes: Fiscal Year 1997 Report for Task Plan SR-16WT-31, Task A

    SciTech Connect

    Andrews, M.K.; Harbour, J.R.; Edwards, T.B.; Workman, P.J.

    1997-10-01

    Through the Tanks Focus Area, the Office of Science and Technology has funded the Savannah River Technology Center (SRTC) and the Oak Ridge National Laboratory (ORNL) to develop formulations which can incorporate sludges from Oak Ridge (OR) Tank Farms into an immobilized waste form. SRTC has been developing a glass waste form, while ORNL has been developing a grout waste form for the tank farms sludges. The four tank farms included in this task are: Melton Valley Storage Tanks (MVST), Bethel Valley Evaporator Service Tanks (BVEST), Gunite and Associated Tanks (GAAT)and Old Hydrofracture Tanks (OHF). The first element of the SRTC task for FY97 was to develop a glass formulation to immobilize a blended sludge from the MVST and the BVEST. ORNL had previously developed a soda-lime-silicate (SLS) glass for the MVST sludge. SRTC has reproduced this work and expanded on it for the blended MVST/BVEST sludge. SRTC also performed a durability test on the resultant glasses. The normalized sodium and silicon leachate concentrations for the soda lime silica glasses readily met the Environmental Assessment glass (a borosilicate glass) benchmark limits for these two elements. Additional efforts at the SRTC included the verification of the glass formulation prior to the ORNL radioactive demonstration and technical consultations during the radioactive demonstration. However, the major emphasis for SRTC in FY97 was on the second element of this task, the overall blended average of the tank farms. The second element focused on developing a glass formulation which would immobilize a sludge with a composition obtained from averaging the contents of all four tank farms (composite composition). Although blending the contents of all four tank farms is not feasible, this average composition provides a basis from which to develop a glass formulation. Once a frit formulation was developed which produced a durable glass waste form at relatively high waste loadings, then a statistically

  18. LABORATORY REPORT ON THE REMOVAL OF PERTECHNETATE FROM TANK 241-AN-105 SIMULANT USING PUROLITE A530E

    SciTech Connect

    DUNCAN JB; HAGERTY KJ; MOORE WP; JOHNSON JM

    2012-06-29

    This effort falls under the technetium management initiative and will provide data for those who will make decisions regarding the handling and disposition of technetium. To that end, the objective of this effort is to challenge Purolite{reg_sign} A530E against a double-shell tank simulant from tank 241-AN-105 spiked with pertechnetate (TcO{sub 4}{sup -}). The Purolite{reg_sign} A530E is commercially available and is currently being used at the 200 West Pump and Treat Groundwater Treatment Plant to remove pertechnetate. It has been demonstrated that Purolite{reg_sign} A530E is highly effective in removing TcO{sub 4}{sup -} from a water matrix. Purolite{reg_sign} A530E is the commercial product of the Oak Ridge National Laboratory's Biquat{trademark} resin. Further work has demonstrated that technetium-loaded A530E achieves a leachability index in Cast Stone of 12.5 (RPP-RPT-39195, Assessment of Technetium Leachability in Cement-Stabilized Basin 43 Groundwater Brine).

  19. LABORATORY REPORT ON THE REMOVAL OF PERTECHNETATE FROM TANK 241-AN-105 SIMULANT USING PUROLITE A530E

    SciTech Connect

    DUNCAN JB; HAGERTY KJ, MOORE WP; JOHNSON JM

    2012-04-17

    This report documents the laboratory testing and analyses as directed under the test plan, LAB-PLN-11-00010, Evaluation of Technetium Ion Exchange Material against Hanford Double Shell Tank Supernate Simulate with Pertechnetate. Technetium (Tc-99) is a major fission product from nuclear reactors, and because it has few applications outside of scientific research, most of the technetium will ultimately be disposed of as nuclear waste. The radioactive decay of Tc-99 to ruthenium 99 (Ru-99) produces a low energy {beta}{sup -} particle (0.1 MeV max). However, due to its fairly long half-life (t{sub 1/2} = 2.13E05 years), Tc-99 is a major source of radiation in low-level waste (UCRL-JRNL-212334, Current Status of the Thermodynamic Data for Technetium and its Compounds and Aqueous Species). Technetium forms the soluble oxy anion, TcO{sub 4}{sup -} under aerobic conditions. This anion is very mobile in groundwater and poses a health risk (ANL, Radiological and Chemical Fact Sheets to Support Health Risk Analyses for Contaminated Areas). It has been demonstrated that Purolite{reg_sign} A530E is highly effective in removing TcO{sub 4}{sup -} from a water matrix (RPP-RPT-23199, The Removal of Technetium-99 from the Effluent Treatment Facility Basin 44 Waste Using Purolite A-530E, Reillex HPQ, and Sybron IONAC SR-7 Ion Exchange Resins). Purolite{reg_sign} A530E is the commercial product of the Oak Ridge National Laboratory's Biquat{trademark} resin (Gu, B. et. ai, Development of Novel Bifunctional Anion-Exchange Resins with Improved Selectivity for Pertechnetate Sorption from Contaminated Groundwater). Further work has demonstrated that technetium-loaded A530E achieves a leachability index in Cast Stone of 12.5 (ANSI/ASN-16.1-2003, Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-term Test Procedure) as reported in RPP-RPT-39195, Assessment of Technetium Leachability in Cement-Stabilized Basin 43 Groundwater Brine. This effort falls under

  20. Development of an inventory/archive program for the retention, management, and disposition of tank characterization samples at the 222-S laboratory

    SciTech Connect

    Seidel, C.M.

    1998-04-29

    The Hanford Tank Waste Remediation Systems (TWRS) Characterization Program is responsible for coordinating the sampling and analysis of the 177 large underground storage tanks at the Hanford site. The 222-S laboratory has been the primary laboratory for chemical analysis of this highly-radioactive material and has been accumulating these samples for many years. As part of the Fiscal Year 1998 laboratory work scope, the 222-S laboratory has performed a formal physical inventory of all tank characterization samples which are currently being stored. In addition, an updated inventory/archive program has been designed. This program defines sample storage, retention, consolidation, maintenance, and disposition activities which will ensure that the sample integrity is preserved to the greatest practical extent. In addition, the new program provides for continued availability of waste material in a form which will be useful for future bench-scale studies. Finally, when the samples have exceeded their useful lifetime, the program provides for sample disposition from,the laboratory in a controlled, safe and environmentally compliant manner. The 222-S laboratory maintains custody over samples of tank waste material which have been shipped to the laboratory for chemical analysis. The storage of these samples currently requires an entire hotcell, fully dedicated to sample archive storage, and is rapidly encroaching on additional hotcell space. As additional samples are received, they are beginning to limit the 222-S laboratory hotcell utility for other activities such as sample extrusion and subsampling. The 222-S laboratory tracks the number of sample containers and the mass of each sample through an internal database which has recently been verified and updated via a physical inventory.

  1. Design assessment for the Melton Valley Storage Tanks capacity increase at Oak Ridge National Laboratory under the Federal Facility Agreement, Oak Ridge, Tennessee

    SciTech Connect

    1995-11-01

    This project was initiated to find ways to increase storage capacity for the liquid low-level waste (LLLW) system at the Oak Ridge National Laboratory and satisfy the Federal Facility Agreement (FFA) requirement for the transfer of LLW from existing tank systems not in full FFA compliance.

  2. Temporal GPR imaging of an ethanol release within a laboratory-scaled sand tank

    NASA Astrophysics Data System (ADS)

    Glaser, D. R.; Werkema, D. D.; Versteeg, R. J.; Henderson, R. D.; Rucker, D. F.

    2012-11-01

    Within the last decade efforts in geophysical detection and monitoring of fossil fuel releases into the subsurface have shown increasing success, including the ability to geophysically detect and delineate enhanced and natural biodegradation and remediation activities. The substitution of biofuels, such as ethanol, for fossil fuels is becoming persistent in the national and international marketplaces making it subject to the same types of accidental releases and exposure scenarios currently associated with the transport and storage of fossil fuels. Thus, there is interest from both academics and regulators to investigate the feasibility of applying geophysical methodologies to biofuel releases. In this study, we performed experimental and numerical investigations on the feasibility of using ground penetrating radar (GPR) to monitor the migration of an ethanol release. A tank scale model of a closed hydrologic system was prepared with Ottawa sand and instrumented with an automated gantry measurement apparatus for time-lapse measurement of zero offset and coincident GPR reflections on multiple horizontal planes. Measurements were acquired in the unsaturated and saturated zones throughout the injection and transport of the ethanol release. The results of the monitoring suggest a measureable contrast within both time and frequency domains of the GPR data coincident with the ethanol release and subsequent migration. We conclude that the monitoring of ethanol in a sand matrix at various levels of saturation is possible with GPR.

  3. Implementation plan for liquid low-level radioactive waste tank systems at Oak Ridge National Laboratory under the Federal Facility Agreement, Oak Ridge, Tennessee

    SciTech Connect

    1995-06-01

    This document is an annual revision of the plans and schedules for implementing the Federal Facility Agreement (FFA) compliance program, originally submitted in ES/ER-17&D1, Federal Facility Agreement Plans and Schedules for Liquid Low-Level Radioactive Waste Tank Systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee. This document summarizes the progress that has been made to date in implementing the plans and schedules for meeting the FFA commitments for the Liquid Low-Level Waste (LLLW) System at Oak Ridge National Laboratory (ORNL). Information presented in this document provides a comprehensive summary to facilitate understanding of the FFA compliance program for LLLW tank systems and to present plans and schedules associated with remediation, through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) process, of LLLW tank systems that have been removed from service. ORNL has a comprehensive program underway to upgrade the LLLW system as necessary to meet the FFA requirements. The tank systems that are removed from service are being investigated and remediated through the CERCLA process. Waste and risk characterizations have been submitted. Additional data will be prepared and submitted to EPA/TDEC as tanks are taken out of service and as required by the remedial investigation/feasibility study (RI/FS) process. Chapter 1 provides general background information and philosophies that lead to the plans and schedules that appear in Chapters 2 through 5.

  4. Dismantlement and removal of Old Hydrofracture Facility bulk storage bins and water tank, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1998-03-01

    The Old Hydrofracture Facility (OHF), located at Oak Ridge National Laboratory (ORNL), was constructed in 1963 to allow experimentation and operations with an integrated solid storage, mixing, and grout injection facility. During its operation, OHF blended liquid low-level waste with grout and used a hydrofracture process to pump the waste into a deep low-permeable shale formation. Since the OHF Facility was taken out of service in 1980, the four bulk storage bins located adjacent to Building 7852 had deteriorated to the point that they were a serious safety hazard. The ORNL Surveillance and Maintenance Program requested and received permission from the US Department of Energy to dismantle the bins as a maintenance action and send the free-released metal to an approved scrap metal vendor. A 25,000-gal stainless steel water tank located at the OHF site was included in the scope. A fixed-price subcontract was signed with Allied Technology Group, Inc., to remove the four bulk storage bins and water tank to a staging area where certified Health Physics personnel could survey, segregate, package, and send the radiologically clean scrap metal to an approved scrap metal vendor. All radiologically contaminated metal and metal that could not be surveyed was packaged and staged for later disposal. Permissible personnel exposure limits were not exceeded, no injuries were incurred, and no health and safety violations occurred throughout the duration of the project. Upon completion of the dismantlement, the project had generated 53,660 lb of clean scrap metal (see Appendix D). This resulted in $3,410 of revenue generated and a cost avoidance of an estimated $100,000 in waste disposal fees.

  5. Test plan: Laboratory-scale testing of the first core sample from Tank 102-AZ

    SciTech Connect

    Morrey, E.V.

    1996-03-01

    The overall objectives of the Radioactive Process/Product Laboratory Testing (RPPLT), WBS 1.2.2.05.05, are to confirm that simulated HWVP feed and glass are representative of actual radioactive HWVP feed and glass and to provide radioactive leaching and glass composition data to WFQ. This study will provide data from one additional NCAW core sample (102-AZ Core 1) for these purposes.

  6. Structural integrity assessments for the category C liquid low-level waste tank systems at the Oak Ridge National Laboratory

    SciTech Connect

    1995-09-01

    This document provides a report of the efforts made to satisfy the Federal Facility Agreement (FFA) for the structural integrity certification of 14 Category C Liquid Low Level Waste (LLLW) Tank Systems on the Oak Ridge Reservation (ORR) in Oak Ridge, Tennessee. Within this document, each tank system is described including the associated pipeline segments evaluated as a part of those tank systems. A separate structural integrity assessment was conducted for each of the LLLW Tank Systems, four of which are located in Melton Valley, and ten of which are located in Bethel Valley. The results of the structural integrity assessments are reported herein. The assessments are based on (1) a review of available tank design drawings, (2) a qualitative assessment of corrosion on the tank and pipelines, and primarily, and (3) leak testing program results. Design plans and specifications were reviewed for a general description of the tanks and associated pipelines. Information of primary significance included tank age, material of construction, tank design and construction specifications. Design plans were also reviewed for the layouts and materials of pipeline constructions, and ages of pipelines. Next, a generic corrosion assessment was conducted for each tank system. Information was gathered, when available, related to the historical use of the tank and the likely contents. The corrosion assessments included a qualitative evaluation of the walls of each tank and pipelines associated with each tank, as well as the welds and joints of the systems. A general discussion of the stainless steel types encountered is included in Section 4.0 of this report. The potential for soils to have caused corrosion is also evaluated within the sections on the individual tank systems.

  7. Risk characterization data manual for Category D inactive liquid low-level waste tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1997-04-01

    This manual reports the results of a risk characterization of Category D inactive liquid low-level radioactive waste (LLLW) at the Oak Ridge National Laboratory (ORNL). The risk characterization is required by the Federal Facility Agreement between the Department of Energy-Oak Ridge Operations Office, the Environmental Protection Agency-Region IV, and the Tennessee Department of Environment and Conservation. The intent of the risk characterization is to determine relative priorities for assessment and remediation. When the scores for all tanks had been weighted and summed, the tanks were ranked in descending order on the basis of their total scores. The highest possible score for a tank is 30. The descending order represents the recommended priorities for evaluation: the higher the score, the higher the priority for evaluation.

  8. Predation and control efficacies of Misgurnus mizolepis (Cypriniformes: Cobitidae) toward Culex pipiens molestus (Diptera: Culicidae) and fish toxicity of temephos in laboratory and septic tank conditions.

    PubMed

    Chae, Seong Chun; Kwon, Young Hyun; Min, Kyung Il; Kim, Hyung Soo; Kim, Nam-Jin; Kim, Jun-Ran; Son, Bong Gi; Ahn, Young-Joon

    2014-07-01

    Culex pipiens molestus Forskal (Diptera: Culicidae) is the dominant mosquito species in septic tanks in South Korea. An assessment was made of the biological control potential of mud loaches, Misgurnus mizolepis Günther (Cypriniformes: Cobitidae), toward Cx. p. molestus larvae in laboratory and septic tanks. Results were compared with those of temephos 20% emulsifiable concentrate. In laboratory tests, all mud loaches survived on sedimentation chamber- and effluent chamber-collected water of aerobic septic tanks (ASTs), whereas all mud loaches died within 3-12 h after introduction into sedimentation chamber- and effluent chamber-collected water of anaerobic septic tanks, Gill hyperplasia and hemorrhages at the bases of pectoral fins were detected in all dead mud loaches. These appeared to have been caused by bacterial disease, rather than the physical and chemical characteristics of the septic tank water. A mud loach consumed an average range of 1,072-1,058 larvae of Cx. p. molestus in the AST water at 24 h. At the manufacturer's recommended rate (10 ml/ton) in the AST water, the temephos formulation did not cause fish mortality. In the AST experiment, predation of mosquito larvae by mud loaches at a release rate of one fish per 900 mosquito larvae resulted in complete mosquito control from the third day after treatment throughout the 18-wk survey period, compared with temephos 20% emulsifiable concentrate-treated AST water (reduction rate, 40% at 28 days after treatment). Reasonable mosquito control in aerobic septic tanks can be achieved by mosquito breeding season stocking of a rate of one mud loach per 900 mosquito larvae.

  9. High Level Waste Tank Farm Replacement Project for the Idaho Chemical Processing Plant at the Idaho National Engineering Laboratory. Environmental Assessment

    SciTech Connect

    Not Available

    1993-06-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0831, for the construction and operation of the High-Level Waste Tank Farm Replacement (HLWTFR) Project for the Idaho Chemical Processing Plant located at the Idaho National Engineering Laboratory (INEL). The HLWTFR Project as originally proposed by the DOE and as analyzed in this EA included: (1) replacement of five high-level liquid waste storage tanks with four new tanks and (2) the upgrading of existing tank relief piping and high-level liquid waste transfer systems. As a result of the April 1992 decision to discontinue the reprocessing of spent nuclear fuel at INEL, DOE believes that it is unlikely that the tank replacement aspect of the project will be needed in the near term. Therefore, DOE is not proposing to proceed with the replacement of the tanks as described in this-EA. The DOE`s instant decision involves only the proposed upgrades aspect of the project described in this EA. The upgrades are needed to comply with Resource Conservation and Recovery Act, the Idaho Hazardous Waste Management Act requirements, and the Department`s obligations pursuant to the Federal Facilities Compliance Agreement and Consent Order among the Environmental Protection Agency, DOE, and the State of Idaho. The environmental impacts of the proposed upgrades are adequately covered and are bounded by the analysis in this EA. If DOE later proposes to proceed with the tank replacement aspect of the project as described in the EA or as modified, it will undertake appropriate further review pursuant to the National Environmental Policy Act.

  10. Preliminary engineering report waste area grouping 5, Old Hydrofracture Facility Tanks content removal project, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1996-06-01

    The Superfund Amendments and Reauthorization Act of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requires a Federal Facilities Agreement (FFA) for federal facilities placed on the National Priorities List. The Oak Ridge Reservation was placed on that list on December 21, 1989, and the agreement was signed in November 1991 by the U.S. Department of Energy (DOE) Oak Ridge Operations Office, the U.S. Environmental Protection Agency (EPA) Region IV, and the Tennessee Department of Environment and Conservation (TDEC). The effective date of the FFA is January 1, 1992. One objective of the FFA is to ensure that liquid low-level waste (LLLW) tanks that are removed from service are evaluated and remediated through the CERCLA process. Five inactive LLLW tanks, designated T-1, T-2, T-3, T-4, and T-9, located at the Old Hydrofracture (OHF) Facility in the Melton Valley area of Oak Ridge National Laboratory (ORNL) have been evaluated and are now entering the remediation phase. As a precursor to final remediation, this project will remove the current liquid and sludge contents of each of the five tanks (System Requirements Document, Appendix A). It was concluded in the Engineering Evaluation/Cost Analysis [EE/CA] for the Old Hydrofracture Facility Tanks (DOE 1996) that sluicing and pumping the contaminated liquid and sludge from the five OHF tanks was the preferred removal action. Evaluation indicated that this alternative meets the removal action objective and can be effective, implementable, and cost-effective. Sluicing and removing the tank contents was selected because this action uses (1) applicable experience, (2) the latest information about technologies and techniques for removing the wastes from the tanks, and (3) activities that are currently acceptable for storage of transuranic (TRU) mixed waste.

  11. Upgrade of 400,000 gallon water storage tank at Argonne National Laboratory-West to UCRL-15910 high hazard seismic requirements

    SciTech Connect

    Griffin, M.J.; Harris, B.G.

    1993-10-01

    As part of the Integral Fast Reactor (IFR) Project at Argonne National Laboratory West (ANL-W), it was necessary to strengthen an existing 400,000 gallon flat-bottom water storage tank to meet UCRL-15910 (currently formulated as DOE Standard DOE-STD-1020-92, Draft) high hazard natural phenomena requirements. The tank was constructed in 1988 and preliminary calculations indicated that the existing base anchorage was insufficient to prevent buckling and potential failure during a high hazard seismic event. General design criteria, including ground motion input, load combinations, etc., were based upon the requirements of UCRL-15910 for high hazard facilities. The analysis and capacity assessment criteria were based on the Generic Implementation Procedure developed by the Seismic Qualification Utilities Group (SQUG). Upgrade modifications, consisting of increasing the size of the Generic Implementation Procedure developed by the Seismic Qualification Utilities Group (SQUG). Upgrade modifications, consisting of increasing the size of the foundation and installing additional anchor bolts and chairs, were necessary to increase the capacity of the tank anchorage/support system. The construction of the upgrades took place in 1992 while the tank remained in service to allow continued operation of the EBR-II reactor. The major phases of construction included the installation and testing of 144 1/14in. {times} 15in., and 366 1in. {times} 16in. epoxied concrete anchors, placement of 220 cubic yards of concrete heavily reinforced, and installation of 24 1-1/2in. {times} 60in. tank anchor bolts and chairs. A follow-up inspection of the tank interior by a diver was conducted to determine if the interior tank coating had been damaged by the chair welding. The project was completed on schedule and within budget.

  12. Maintenance Action Readiness Assessment Plan for Waste Area Grouping 1 inactive Tanks 3001-B, 3004-B, T-30, and 3013 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1995-07-01

    This Readiness Assessment Plan has been prepared to document operational readiness for the maintenance action consisting of remediation of four inactive liquid low-level radioactive tanks in Waste Area Grouping 1 at Oak Ridge National Laboratory. The four tanks to be remediated are Tanks 3001-B, 3004-B, T-30, and 3013. Tanks 3001-B, 3004-B, and T-30 will be removed from the ground. Because of logistical issues associated with excavation and site access, Tank 3013 will be grouted in place and permanently closed. This project is being performed as a maintenance action rather than an action under the Comprehensive Environmental Response, Compensation, and Liability Act, because the risk to human health and environment is well below the US Environmental Protection Agency`s level of concern. The decision to proceed as a maintenance action was documented by an interim action proposed plan, which is included in the administrative record. A Readiness Assessment Team has been assembled to review the criteria deemed necessary to conduct the remediation tasks. These criteria include approval of all plans, acquisition of needed equipment, completion of personnel training, and coordination with plant health and safety personnel. Once the criteria have been met and documented, the task will begin. The readiness assessment is expected to be completed by late July 1995, and the task will begin thereafter.

  13. ADM. Tanks: from left to right: fuel oil tank, fuel ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    ADM. Tanks: from left to right: fuel oil tank, fuel pump house (TAN-611), engine fuel tank, water pump house, water storage tank. Camera facing northwest. Not edge of shielding berm at left of view. Date: November 25, 1953. INEEL negative no. 9217 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  14. EVALUATION OF THE IMPACT OF THE DEFENSE WASTE PROCESSING FACILITY (DWPF) LABORATORY GERMANIUM OXIDE USE ON RECYCLE TRANSFERS TO THE H-TANK FARM

    SciTech Connect

    Jantzen, C.; Laurinat, J.

    2011-08-15

    When processing High Level Waste (HLW) glass, the Defense Waste Processing Facility (DWPF) cannot wait until the melt or waste glass has been made to assess its acceptability, since by then no further changes to the glass composition and acceptability are possible. Therefore, the acceptability decision is made on the upstream feed stream, rather than on the downstream melt or glass product. This strategy is known as 'feed forward statistical process control.' The DWPF depends on chemical analysis of the feed streams from the Sludge Receipt and Adjustment Tank (SRAT) and the Slurry Mix Evaporator (SME) where the frit plus adjusted sludge from the SRAT are mixed. The SME is the last vessel in which any chemical adjustments or frit additions can be made. Once the analyses of the SME product are deemed acceptable, the SME product is transferred to the Melter Feed Tank (MFT) and onto the melter. The SRAT and SME analyses have been analyzed by the DWPF laboratory using a 'Cold Chemical' method but this dissolution did not adequately dissolve all the elemental components. A new dissolution method which fuses the SRAT or SME product with cesium nitrate (CsNO{sub 3}), germanium (IV) oxide (GeO{sub 2}) and cesium carbonate (Cs{sub 2}CO{sub 3}) into a cesium germanate glass at 1050 C in platinum crucibles has been developed. Once the germanium glass is formed in that fusion, it is readily dissolved by concentrated nitric acid (about 1M) to solubilize all the elements in the SRAT and/or SME product for elemental analysis. When the chemical analyses are completed the acidic cesium-germanate solution is transferred from the DWPF analytic laboratory to the Recycle Collection Tank (RCT) where the pH is increased to {approx}12 M to be released back to the tank farm and the 2H evaporator. Therefore, about 2.5 kg/yr of GeO{sub 2}/year will be diluted into 1.4 million gallons of recycle. This 2.5 kg/yr of GeO{sub 2} may increase to 4 kg/yr when improvements are implemented to attain

  15. Tank plan for tank 241-C-104 retrieval testing

    SciTech Connect

    HERTING, D.L.

    1999-05-21

    Tank 241-C-104 has been identified as one of the first tanks to be retrieved for high-level waste pretreatment and immobilization. Retrieval of the tank waste will require dilution. Laboratory tests are needed to determine the amount of dilution required for safe retrieval and transfer of feed. The proposed laboratory tests are described in this document.

  16. Tank 241-SX-103 tank characterization plan

    SciTech Connect

    Homi, C.S.

    1995-03-08

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, Oak Ridge National Laboratory, and PNL tank vapor program. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-SX-103.

  17. Tank 241-U-103 tank characterization plan

    SciTech Connect

    Carpenter, B.C.

    1995-01-24

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, Oak Ridge National Laboratory and PNL tank vapor program. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-U-103.

  18. Surfactant control of gas transfer velocity along an offshore coastal transect: results from a laboratory gas exchange tank

    NASA Astrophysics Data System (ADS)

    Pereira, R.; Schneider-Zapp, K.; Upstill-Goddard, R. C.

    2016-07-01

    Understanding the physical and biogeochemical controls of air-sea gas exchange is necessary for establishing biogeochemical models for predicting regional- and global-scale trace gas fluxes and feedbacks. To this end we report the results of experiments designed to constrain the effect of surfactants in the sea surface microlayer (SML) on the gas transfer velocity (kw; cm h-1), seasonally (2012-2013) along a 20 km coastal transect (North East UK). We measured total surfactant activity (SA), chromophoric dissolved organic matter (CDOM) and chlorophyll a (Chl a) in the SML and in sub-surface water (SSW) and we evaluated corresponding kw values using a custom-designed air-sea gas exchange tank. Temporal SA variability exceeded its spatial variability. Overall, SA varied 5-fold between all samples (0.08 to 0.38 mg L-1 T-X-100), being highest in the SML during summer. SML SA enrichment factors (EFs) relative to SSW were ˜ 1.0 to 1.9, except for two values (0.75; 0.89: February 2013). The range in corresponding k660 (kw for CO2 in seawater at 20 °C) was 6.8 to 22.0 cm h-1. The film factor R660 (the ratio of k660 for seawater to k660 for "clean", i.e. surfactant-free, laboratory water) was strongly correlated with SML SA (r ≥ 0.70, p ≤ 0.002, each n = 16). High SML SA typically corresponded to k660 suppressions ˜ 14 to 51 % relative to clean laboratory water, highlighting strong spatiotemporal gradients in gas exchange due to varying surfactant in these coastal waters. Such variability should be taken account of when evaluating marine trace gas sources and sinks. Total CDOM absorbance (250 to 450 nm), the CDOM spectral slope ratio (SR = S275 - 295/S350 - 400), the 250 : 365 nm CDOM absorption ratio (E2 : E3), and Chl a all indicated spatial and temporal signals in the quantity and composition of organic matter in the SML and SSW. This prompts us to hypothesise that spatiotemporal variation in R660 and its relationship with SA is a consequence of compositional

  19. Laboratory studies of gas generation and potential for tank wall corrosion during blending of high-level wastes at the West Valley Demonstration Project

    SciTech Connect

    Gray, W.J.; Westerman, R.E.

    1995-05-01

    Laboratory experiments were conducted to simulate the transfer of acidic THOREX waste from Tank 8D-4 into the alkaline PUREX waste in Tank 8D-2 at West Valley. The purpose of the experiments was to explore means of minimizing the production of nitric oxide (NO) gas during mixing of the two wastes and to assess the potential for the gas to further react in the vapor space possibly leading to enhanced corrosion of the tank walls. Forty one THOREX/PUREX mixing tests were conducted to explore the effects of stirring rate, pH, THOREX addition rate, THOREX or PUREX dilution, and temperature. The two most important criteria for minimizing NO production were to maintain some degree of agitation and the keep the pH in the PUREX high, preferably >12. Steel corrosion tests were performed in the presence of low partial pressures of NO{sub 2} and liquid water or water vapor. The NO{sub 2} (from oxidation of NO in the vapor space) concentrations were representative of those derived from the THOREX/PUREX mixing tests. It was concluded that no significant corrosion of the tank walls would be expected under the anticipated THOREX/PUREX mixing conditions if the exposure was short (<100 days).

  20. Tank 241-C-103 tank characterization plan

    SciTech Connect

    Schreiber, R.D.

    1994-10-06

    The data quality objective (DQO) process was chosen as a tool to be used to identify the sampling analytical needs for the resolution of safety issues. A Tank Characterization Plant (TCP) will be developed for each double shell tank (DST) and single-shell tank (SST) using the DQO process. There are four Watch list tank classifications (ferrocyanide, organic salts, hydrogen/flammable gas, and high heat load). These classifications cover the six safety issues related to public and worker health that have been associated with the Hanford Site underground storage tanks. These safety issues are as follows: ferrocyanide, flammable gas, organic, criticality, high heat, and vapor safety issues. Tank C-103 is one of the twenty tanks currently on the Organic Salts Watch List. This TCP will identify characterization objectives pertaining to sample collection, hot cell sample isolation, and laboratory analytical evaluation and reporting requirements in accordance with the appropriate DQO documents. In addition, the current contents and status of the tank are projected from historical information. The relevant safety issues that are of concern for tanks on the Organic Salts Watch List are: the potential for an exothermic reaction occurring from the flammable mixture of organic materials and nitrate/nitrite salts that could result in a release of radioactive material and the possibility that other safety issues may exist for the tank.

  1. Deployment of a fluidic pulse jet mixing system for horizontal waste storage tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Kent, T.E.; Hylton, T.D.; Taylor, S.A.; Moore, J.W.

    1998-08-01

    A fluidic pulse jet mixing system, designed and fabricated by AEA Technology, was successfully demonstrated for mobilization of remote-handled transuranic (RH-TRU) sludge for retrieval from three 50,000-gal horizontal waste storage tanks (W-21, W-22, and W-23) at Oak Ridge National Laboratory (ORNL). The pulse jet system is unique because it does not contain any moving parts except for some solenoid valves which can be easily replaced if necessary. The pulse jet system consisted of seven modular equipment skids and was installed and commissioned in about 7 weeks. The system used specially designed fluidic jet pumps and charge vessels, along with existing submerged nozzles for mixing the settled sludges with existing supernate in the tank. The operation also used existing piping and progressive cavity pumps for retrieval and transfer of the waste mixtures. The pulse jet system operated well and experienced no major equipment malfunctions. The modular design, use of quick-connect couplings, and low-maintenance aspects of the system minimized radiation exposure during installation and operation of the system. The extent of sludge removal from the tanks was limited by the constraints of using the existing tank nozzles and the physical characteristics of the sludge. Removing greater than 98% of this sludge would require aggressive use of the manual sluicer (and associated water additions), a shielded sluicer system that utilizes supernate from existing inventory, or a more costly and elaborate robotic retrieval system. The results of this operation indicate that the pulse jet system should be considered for mixing and bulk retrieval of sludges in other horizontal waste tanks at ORNL and US Department of Energy sites.

  2. Work plan and health and safety plan for Building 3019B underground storage tank at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Burman, S.N.; Brown, K.S.; Landguth, D.C.

    1992-08-01

    As part of the Underground Storage Tank Program at the Department of Energy`s Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, this Health and Safety Plan has been developed for removal of the 110-gal leaded fuel underground storage tank (UST) located in the Building 3019B area at ORNL This Health and Safety Plan was developed by the Measurement Applications and Development Group of the Health and Safety Research Division at ORNL The major components of the plan follow: (1) A project description that gives the scope and objectives of the 110-gal tank removal project and assigns responsibilities, in addition to providing emergency information for situations occurring during field operations; (2) a health and safety plan in Sect. 15 for the Building 3019B UST activities, which describes general site hazards and particular hazards associated with specific tasks, personnel protection requirements and mandatory safety procedures; and (3) discussion of the proper form completion and reporting requirements during removal of the UST. This document addresses Occupational Safety and Health Administration (OSHA) requirements in 29 CFR 1910.120 with respect to all aspects of health and safety involved in a UST removal. In addition, the plan follows the Environmental Protection Agency (EPA) QAMS 005/80 (1980) format with the inclusion of the health and safety section (Sect. 15).

  3. Integration of remediation strategy with waste management capabilities and regulatory drivers for radioactive waste storage tanks at the Oak Ridge National Laboratory

    SciTech Connect

    Baxter, J.T.; Hepworth, H.K.; Hooyman, J.H.

    1995-04-01

    This paper addresses the plans and strategies for remediation of the Liquid Low-Level Waste (LLLW) system tanks that have been removed from service at the Oak Ridge National Laboratory (ORNL). The Superfund Amendments and Reauthorization Act of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requires a Federal Facility Agreement (FFA) for federal facilities placed on the National Priorities List. The Oak Ridge Reservation was placed on that list on December 21, 1989, and the agreement was signed in November 1991 by the U.S. Department of Energy Oak Ridge Operations Office (DOE-ORO), the EPA-Region IV, and the Tennessee Department of Environment and Conservation (TDEC). The effective date of the FFA is January 1, 1992. One requirement of the FFA is that LLLW tanks that are removed from service must be evaluated and remediated through the CERCLA process. The Environmental Restoration Program intends to meet this requirement by using a {open_quotes}streamlined{close_quote} approach for selected tanks. This approach will combine the CERCLA Site Investigation. Remedial Action, Feasibility Study, and Proposed Plan requirements into a single Interim Proposed Plan document. This streamlined approach is expected to reduce the time required to complete the regulatory process while attaining acceptable risk reduction in a cost-effective way.

  4. Work plan and health and safety plan for Building 3019B underground storage tank at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Burman, S.N.; Brown, K.S.; Landguth, D.C.

    1992-08-01

    As part of the Underground Storage Tank Program at the Department of Energy's Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, this Health and Safety Plan has been developed for removal of the 110-gal leaded fuel underground storage tank (UST) located in the Building 3019B area at ORNL This Health and Safety Plan was developed by the Measurement Applications and Development Group of the Health and Safety Research Division at ORNL The major components of the plan follow: (1) A project description that gives the scope and objectives of the 110-gal tank removal project and assigns responsibilities, in addition to providing emergency information for situations occurring during field operations; (2) a health and safety plan in Sect. 15 for the Building 3019B UST activities, which describes general site hazards and particular hazards associated with specific tasks, personnel protection requirements and mandatory safety procedures; and (3) discussion of the proper form completion and reporting requirements during removal of the UST. This document addresses Occupational Safety and Health Administration (OSHA) requirements in 29 CFR 1910.120 with respect to all aspects of health and safety involved in a UST removal. In addition, the plan follows the Environmental Protection Agency (EPA) QAMS 005/80 (1980) format with the inclusion of the health and safety section (Sect. 15).

  5. Evaluation of the Molten Salt Reactor Experiment drain tanks for reuse in salt disposal, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1998-05-01

    This report was prepared to identify the source documentation used to evaluate the drain tanks in the Molten Salt Reactor Experiment (MSRE) at Oak Ridge National Laboratory (ORNL). The evaluation considered the original quality of the tanks, their service history, and their intended use during the removal of fluoride salts. It also includes recommendations for a quality verification plan. The estimates of corrosion damage to the salt containing system at the MSRE are low enough to lend optimism that the system will be fit for its intended use, which is disposal of the salt by transferring it to transport containers. The expected corrosion to date is estimated between 10 and 50 mil, or 2 to 10% of the shell wall. The expected corrosion rate when the tanks are used to remove the salt at 110 F is estimated to be .025 to 0.1 mil per hour of exposure to HF and molten salt. To provide additional assurance that the estimates of corrosion damage are accurate, cost effective nondestructive examination (NDE) has been recommended. The NDE procedures are compared with industry standards and give a perspective for the extent of additional measures taken in the recommendation. A methodology for establishing the remaining life has been recommended, and work is progressing towards providing an engineering evaluation based upon thickness and design conditions for the future use of the tanks. These extra measures and the code based analysis will serve to define the risk of salt or radioactive gases leaking during processing and transfer of the salt as acceptable.

  6. Extended Cold Testing of a Russian Pulsating Mixer Pump at the Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Lewis, BE

    2002-12-23

    The effectiveness of a mixer is dependent on the size of the tank to be mixed, the characteristics of the waste, and the operating conditions. Waste tanks throughout the U.S. Department of Energy Complex require mixing and mobilization systems capable of (1) breaking up and suspending materials that are difficult to mix and pump, without introducing additional liquids into the tank; (2) complementing and augmenting the performance of other remotely operated and/or robotic waste retrieval systems; and (3) operating in tanks with various quantities of waste. The Oak Ridge Russian pulsating mixer pump (PMP) system was designed with the flexibility to permit deployment in a variety of cylindrical tanks. The PMP was installed at the Tanks Technology Cold Test Facility at the Oak Ridge National Laboratory (ORNL) to assess the performance of the system over an extended range of operating conditions, including supply pressures up to 175 psig. Previously conducted cold tests proved the applicability of the PMP for deployment in ORNL gunite tank TH-4. The previous testing and hot demonstrations had been limited to operating at air supply pressures of <100 psig. The extended cold testing of the Russian PMP system showed that the system was capable of mobilizing waste simulants in tanks in excess of 20-ft diam. The waste simulant used in these tests was medium-grain quartz sand. The system was successfully installed, checked out, and operated for 406 pulse discharge cycles. Only minor problems (i.e., a sticking air distributor valve and a few system lockups) were noted. Some improvements to the design of the air distributor valve may be needed to improve reliability. The air supply requirements of the PMP during the discharge cycle necessitated the operation of the system in single pulse discharge cycles to allow time for the air supply reservoir to recharge to the required pressure. During the test program, the system was operated with sand depths of 2, 4, and 4.5 in.; at

  7. Tanks and Tank Troops

    DTIC Science & Technology

    1982-03-01

    operational in the Bundeswehr. These include the well-known U.S. M113 APC, the HS-30 APC, developed by the Swiss company Hispano- Suiza , as well as the...powered by the Leyland L-60 engine, and the French AMX-30, powered by the Hispano- Suiza HS-110 engine. The new Japanese STB-6 tank (ඒ") is...of all foreign series-produced tank engines. A complete tank engine replacement can be performed in four hours. The Hispano- Suiza HS-110 engine

  8. Utilization of the MPI Process for in-tank solidification of heel material in large-diameter cylindrical tanks

    SciTech Connect

    Kauschinger, J.L.; Lewis, B.E.

    2000-01-01

    A major problem faced by the US Department of Energy is remediation of sludge and supernatant waste in underground storage tanks. Exhumation of the waste is currently the preferred remediation method. However, exhumation cannot completely remove all of the contaminated materials from the tanks. For large-diameter tanks, amounts of highly contaminated ``heel'' material approaching 20,000 gal can remain. Often sludge containing zeolite particles leaves ``sand bars'' of locally contaminated material across the floor of the tank. The best management practices for in-tank treatment (stabilization and immobilization) of wastes require an integrated approach to develop appropriate treatment agents that can be safely delivered and mixed uniformly with sludge. Ground Environmental Services has developed and demonstrated a remotely controlled, high-velocity jet delivery system termed, Multi-Point-Injection (MPI). This robust jet delivery system has been field-deployed to create homogeneous monoliths containing shallow buried miscellaneous waste in trenches [fiscal year (FY) 1995] and surrogate sludge in cylindrical (FY 1998) and long, horizontal tanks (FY 1999). During the FY 1998 demonstration, the MPI process successfully formed a 32-ton uniform monolith of grout and waste surrogates in about 8 min. Analytical data indicated that 10 tons of zeolite-type physical surrogate were uniformly mixed within a 40-in.-thick monolith without lifting the MPI jetting tools off the tank floor. Over 1,000 lb of cohesive surrogates, with consistencies similar to Gunite and Associated Tank (GAAT) TH-4 and Hanford tank sludges, were easily intermixed into the monolith without exceeding a core temperature of 100 F during curing.

  9. Nutrient removal by up-scaling a hybrid floating treatment bed (HFTB) using plant and periphyton: From laboratory tank to polluted river.

    PubMed

    Liu, Junzhuo; Wang, Fengwu; Liu, Wei; Tang, Cilai; Wu, Chenxi; Wu, Yonghong

    2016-05-01

    Planted floating treatment bed (FTB) is an innovative technique of removing nutrients from polluted water but limited in deep water and cold seasons. Periphyton was integrated into FTB for a hybrid floating treatment bed (HFTB) to improve its nutrient removal capacity. To assess its potential for treating nutrient-polluted rivers, HFTB was up-scaled from 5L laboratory tanks to 350L outdoor tanks and then to a commercial-scale 900m section of polluted river. Plants and periphyton interacted in HFTB with periphyton limiting plant root growth and plants having shading effects on periphyton. Non-overlapping distribution of plants and periphyton can minimize the negative interactions in HFTB. HFTB successfully kept TN and TP of the river at less than 2.0 and 0.02mgL(-1), respectively. This study indicates that HFTB can be easily up-scaled for nutrients removal from polluted rivers in different seasons providing a long-term, environmentally-friendly method to remediate polluted ecosystems.

  10. Root cause analysis for waste area grouping 1, Batch I, Series 1 Tank T-30 project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1996-08-01

    Four inactive liquid low-level waste (LLLW) tanks were scheduled for remedial actions as the Batch L Series I Tank Project during fiscal year (FY) 1995. These tanks are 3001-B, 3004-B, T-30, and 3013. The initial tank remediation project was conducted as a maintenance action. One project objective was to gain experience in remediation efforts (under maintenance actions) to assist in conducting remedial action projects for the 33 remaining inactive LLLW tanks. Batch I, Series 1 project activities resulted in the successful remediation of tanks 3001-B, 3004-B, and 3013. Tank T-30 remedial actions were halted as a result of information obtained during waste characterization activities. The conditions discovered on tank T-30 would not allow completion of tank removal and smelting as originally planned. A decision was made to conduct a root cause analysis of Tank T-30 events to identify and, where possible, correct weaknesses that, if uncorrected, could result in similar delays for completion of future inactive tank remediation projects. The objective of the analysis was to determine why a portion of expected project end results for Tank T-30 were not fully achieved. The root cause analysis evaluates project events and recommends beneficial improvements for application to future projects. This report presents the results of the Batch I, Series root cause analysis results and makes recommendations based on that analysis.

  11. TANK 5 SAMPLING

    SciTech Connect

    Vrettos, N; William Cheng, W; Thomas Nance, T

    2007-11-26

    Tank 5 at the Savannah River Site has been used to store high level waste and is currently undergoing waste removal processes in preparation for tank closure. Samples were taken from two locations to determine the contents in support of Documented Safety Analysis (DSA) development for chemical cleaning. These samples were obtained through the use of the Drop Core Sampler and the Snowbank Sampler developed by the Engineered Equipment & Systems (EES) group of the Savannah River National Laboratory (SRNL).

  12. Tank 241-U-202 tank characterization plan

    SciTech Connect

    Schreiber, R.D.

    1995-02-21

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 222-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-U-202.

  13. Tank 241-U-201 tank characterization plan

    SciTech Connect

    Schreiber, R.D.

    1995-02-21

    This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 22-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-U-201.

  14. 1996 structural integrity assessments for the Category C Liquid Low-Level Waste Tank Systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1996-09-01

    This document provides a report of the efforts made to satisfy the Federal Facility Agreement for the structural integrity certification of ten Category C Liquid Low Level Waste (LLLW) tank systems on the Oak Ridge Reservation in Oak Ridge, Tennessee. Within this document, each Category C tank system is described including the associated pipeline segments evaluated as a part of those tank systems. A separate structural integrity assessment was conducted for each of the LLLW Tank Systems, four of which are located in Melton Valley, and six of which are located in Bethel Valley. The results of the structural integrity assessments are reported herein. The assessments are based on (1) a review of available tank design drawings, (2) a qualitative assessment of corrosion on the tank and pipelines, and primarily (3) leak testing program results.

  15. Tank 48 - Chemical Destruction

    SciTech Connect

    Simner, Steven P.; Aponte, Celia I.; Brass, Earl A.

    2013-01-09

    Small tank copper-catalyzed peroxide oxidation (CCPO) is a potentially viable technology to facilitate the destruction of tetraphenylborate (TPB) organic solids contained within the Tank 48H waste at the Savannah River Site (SRS). A maturation strategy was created that identified a number of near-term development activities required to determine the viability of the CCPO process, and subsequent disposition of the CCPO effluent. Critical activities included laboratory-scale validation of the process and identification of forward transfer paths for the CCPO effluent. The technical documentation and the successful application of the CCPO process on simulated Tank 48 waste confirm that the CCPO process is a viable process for the disposition of the Tank 48 contents.

  16. VIEW OF PDP TANK TOP, LEVEL 0’, WITH LTR TANK ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    VIEW OF PDP TANK TOP, LEVEL 0’, WITH LTR TANK TOP ON LEFT, LOOKING NORTHEAST. CRANE AND VERTICAL HOISTING ELEMENTS AT TOP - Physics Assembly Laboratory, Area A/M, Savannah River Site, Aiken, Aiken County, SC

  17. Tank characterization report for Single-Shell Tank T-102

    SciTech Connect

    Remund, K.M.; Hartley, S.A.; Toth, J.J.; Tingey, J.M.; Heasler, P.G.; Ryan, F.M.; Simpson, B.C.

    1994-09-01

    Tank 241-T-102 (hereafter referred to as T-102) is a 530,000 gallon single-shell waste tank located in the 200 West T Tank farm at the Hanford Site. In 1993, two cores were taken from this tank and analysis of the cores was conducted by Battelle`s 325-A Laboratory. Characterization of the waste in this tank was conducted to support Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-44-05. Tank T-102 was constructed in 1943 and put into service in 1945; it is the second tank in a cascade system with Tanks T-101 and T-103. During its process history, Tank T-102 received mostly Metal Waste (MW) from the Bismuth Phosphate Process and Coating Waste (CW) from the REDOX Process via the cascade from Tank T-101 and in transfers from Tank C-102. In 1956, the MW was removed from T-102 by pumping and sluicing`. This tank was declared inactive and retired from service in 1976. In 1981, intrusion prevention and stabilization measures were taken to isolate the waste in T-102. The tank presently contains approximately 121,100 liters (32,000 gallons) of liquid and sludge-like waste. Historically, there are no unreviewed safety issues associated with this tank and none were revealed after reviewing the data from the latest core sampling event in 1993. An extensive set of analytical measurements was performed on the core composites. The major constituents (>0.5 wt%) of the waste are water, aluminum, sodium, iron, and nitrate, ordered from the largest concentration to the smallest. The concentrations and inventories of these and other constituents are given. The results of the chemical analyses have been compared to the dangerous waste codes in the Washington Dangerous Waste Regulations (WAC 173-303).

  18. Results of Hg speciation testing on tank 39 and 1Q16 tank 50 samples

    SciTech Connect

    Bannochie, C. J.

    2016-03-07

    The Savannah River National Laboratory (SRNL) was tasked with preparing and shipping samples for Hg speciation by Eurofins Frontier Global Sciences, Inc. in Seattle, WA on behalf of the Savannah River Remediation (SRR) Mercury Task Team.i,ii The seventeenth shipment of samples was designated to include two Tank 39 samples and the 1Q16 Tank 50 Quarterly WAC sample. The surface Tank 39 sample was pulled at 262.1” from the tank bottom, and the depth Tank 39 sample was pulled at 95” from the tank bottom. The 1Q16 Tank 50 WAC sample was drawn from the 1-L variable depth sample received by SRNL.

  19. Tank 12H residuals sample analysis report

    SciTech Connect

    Oji, L. N.; Shine, E. P.; Diprete, D. P.; Coleman, C. J.; Hay, M. S.

    2015-06-11

    The Savannah River National Laboratory (SRNL) was requested by Savannah River Remediation (SRR) to provide sample preparation and analysis of the Tank 12H final characterization samples to determine the residual tank inventory prior to grouting. Eleven Tank 12H floor and mound residual material samples and three cooling coil scrape samples were collected and delivered to SRNL between May and August of 2014.

  20. Old hydrofracture facility tanks contents removal action operations plan at the Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 1: Text. Volume 2: Checklists and work instructions

    SciTech Connect

    1998-05-01

    This Operations Plan summarizes the operating activities for transferring contents of five low-level (radioactive) liquid waste storage tanks associated with the Old Hydrofracture Facility (OHF) to the Melton Valley Storage Tanks (MVST) for secure storage. The transfer will be accomplished through sluicing and pumping operations which are designed to pump the slurry in a closed circuit system using a sluicing nozzle to resuspend the sludge. Once resuspended, the slurry will be transferred to the MVST. The report documenting the material transfer will be prepared after transfer of the tank materials has been completed. The OBF tanks contain approximately 52,600 gal (199,000 L) of low-level radioactive waste consisting of both sludge and supernatant. This material is residual from the now-abandoned grout injection operations conducted from 1964 to 1980. Total curie content is approximately 30,000 Ci. A sluicing and pumping system has been specifically designed for the OHF tanks contents transfer operations. This system is remotely operated and incorporates a sluicing nozzle and arm (Borehole Miner) originally designed for use in the mining industry. The Borehole Miner is an in-tank device designed to deliver a high pressure jet spray via an extendable nozzle. In addition to removing the waste from the tanks, the use of this equipment will demonstrate applicability for additional underground storage tank cleaning throughout the U.S. Department of Energy complex. Additional components of the complete sluicing and pumping system consist of a high pressure pumping system for transfer to the MVST, a low pressure pumping system for transfer to the recycle tank, a ventilation system for providing negative pressure on tanks, and instrumentation and control systems for remote operation and monitoring.

  1. Think Tanks

    NASA Technical Reports Server (NTRS)

    2001-01-01

    A new inspection robot from Solex Robotics Systems was designed to eliminate hazardous inspections of petroleum and chemical storage tanks. The submersible robot, named Maverick, is used to inspect the bottoms of tanks, keeping the tanks operational during inspection. Maverick is able to provide services that will make manual tank inspections obsolete. While the inspection is conducted, Maverick's remote human operators remain safe outside of the tank. The risk to human health and life is now virtually eliminated. The risk to the environment is also minimal because there is a reduced chance of spillage from emptying and cleaning the tanks, where previously, tons of pollutants were released through the process of draining and refilling.

  2. EM-50 Tanks Focus Area retrieval process development and enhancements. FY97 technology development summary report

    SciTech Connect

    Rinker, M.W.; Bamberger, J.A.; Alberts, D.G.

    1997-09-01

    The Retrieval Process Development and Enhancements (RPD and E) activities are part of the US Department of Energy (DOE) EM-50 Tanks Focus Area, Retrieval and Closure program. The purpose of RPD and E is to understand retrieval processes, including emerging and existing technologies, and to gather data on these processes, so that end users have requisite technical bases to make retrieval decisions. Technologies addressed during FY97 include enhancements to sluicing, the use of pulsed air to assist mixing, mixer pumps, innovative mixing techniques, confined sluicing retrieval end effectors, borehole mining, light weight scarification, and testing of Russian-developed retrieval equipment. Furthermore, the Retrieval Analysis Tool was initiated to link retrieval processes with tank waste farms and tank geometric to assist end users by providing a consolidation of data and technical information that can be easily assessed. The main technical accomplishments are summarized under the following headings: Oak Ridge site-gunite and associated tanks treatability study; pulsed air mixing; Oak Ridge site-Old Hydrofracture Facility; hydraulic testbed relocation; cooling coil cleaning end effector; light weight scarifier; innovative tank mixing; advanced design mixer pump; enhanced sluicing; Russian retrieval equipment testing; retrieval data analysis and correlation; simulant development; and retrieval analysis tool (RAT).

  3. Influence of Light Intensity and Temperature on Cultivation of Microalgae Desmodesmus Communis in Flasks and Laboratory-Scale Stirred Tank Photobioreactor

    NASA Astrophysics Data System (ADS)

    Vanags, J.; Kunga, L.; Dubencovs, K.; Galvanauskas, V.; Grīgs, O.

    2015-04-01

    Optimization of the microalgae cultivation process and of the bioprocess in general traditionally starts with cultivation experiments in flasks. Then the scale-up follows, when the process from flasks is transferred into a laboratory-scale bioreactor, in which further experiments are performed before developing the process in a pilot-scale reactor. This research was done in order to scale-up the process from a 0.4 1 shake flask to a 4.0 1 laboratory-scale stirred-tank photobioreactor for the cultivation of Desmodesmus (D.) communis microalgae. First, the effect of variation in temperature (21-29 ºC) and in light intensity (200-600 μmol m-2s-1) was studied in the shake-flask experiments. It was shown that the best results (the maximum biomass concentration of 2.72 g 1-1 with a specific growth rate of 0.65 g g-1d-1) can be achieved at the cultivation temperature and light intensity being 25 °C and 300 μmol m2s-1, respectively. At the same time, D. communis cultivation under the same conditions in stirred-tank photobioreactor resulted in average volumetric productivities of biomass due to the light limitation even when the light intensity was increased during the experiment (the maximum biomass productivity 0.25 g 1-1d-1; the maximum biomass concentration 1.78 g 1-1). Mikroaļģu kultivēšanas procesa optimizēšana parasti sākas ar kultivēšanas eksperimentiem kolbās. Tālāk seko procesa pārnese uz laboratorijas mēroga fotobioreaktoru, kurā tiek veikti tālāki eksperimenti, pirms tiek izveidots pilota mēroga reaktors. Šis pētījums tika veikts ar mērķi, pārnest Desmodesmus communis kultivēšanas procesu no 0.4 1 kolbas uz 4.0 1 laboratorijas fotobioreaktoru. Vispirms tika pētīta dažādu temperatūru (21-29 ºC) un gaismas intensitātes (200-600 μmol m-2s-1) ietekme uz aļģu biomasu veicot eksperimentus kolbās. Labākie rezultāti (maksimālā biomasas koncentrācija 2.72 g 1-1; īpatnējais augšanas ātrums 0.65 g g-1d-1) sasniegti, kad

  4. Federal Facility Agreement plans and schedules for liquid low-level radioactive waste tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Not Available

    1993-06-01

    The Superfund Amendments and Reauthorization Act of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requires a Federal Facility Agreement (FFA) for federal facilities placed on the National Priorities List. The Oak Ridge Reservation was placed on that list on December 21, 1989, and the agreement was signed in November 1991 by the Department of Energy Oak Ridge Field Office (DOE-OR), the US Environmental Protection Agency (EPA)-Region IV, and the Tennessee Department of Environment and Conservation (TDEC). The effective date of the FFA was January 1, 1992. Section 9 and Appendix F of the agreement impose design and operating requirements on the Oak Ridge National Laboratory (ORNL) liquid low-level radioactive waste (LLLW) tank systems and identify several plans, schedules, and assessments that must be submitted to EPA/TDEC for review or approval. The initial issue of this document in March 1992 transmitted to EPA/TDEC those plans and schedules that were required within 60 to 90 days of the FFA effective date. The current revision of this document updates the plans, schedules, and strategy for achieving compliance with the FFA, and it summarizes the progress that has been made over the past year. Chapter 1 describes the history and operation of the ORNL LLLW System, the objectives of the FFA, the organization that has been established to bring the system into compliance, and the plans for achieving compliance. Chapters 2 through 7 of this report contain the updated plans and schedules for meeting FFA requirements. This document will continue to be periodically reassessed and refined to reflect newly developed information and progress.

  5. Tank 241-C-101 vapor sampling and analysis tank characterization report

    SciTech Connect

    Huckaby, J.L.

    1995-05-31

    Tank C-101 headspace gas and vapor samples were collected and analyzed to help determine the potential risks of fugitive emissions to tank farm workers. Gas and vapor samples from the Tank C-101 headspace were collected on July 7, 1994 using the in situ sampling (ISS) method, and again on September 1, 1994 using the more robust vapor sampling system (VSS). Gas and vapor concentrations in Tank C-101 are influenced by its connections to other tanks and its ventilation pathways. At issue is whether the organic vapors in Tank C-101 are from the waste in that tank, or from Tanks C-102 or C-103. Tank C-103 is on the Organic Watch List; the other two are not. Air from the Tank C-101 headspace was withdrawn via a 7.9-m long heated sampling probe mounted in riser 8, and transferred via heated tubing to the VSS sampling manifold. The tank headspace temperature was determined to be 34.0 C, and all heated zones of the VSS were maintained at approximately 50 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, Pacific Northwest Laboratories, and Oregon Graduate Institute of Science and Technology through a contract with Sandia National Laboratories. The 39 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 14 trip blanks and 2 field blanks provided by the laboratories.

  6. Federal Facility Agreement plans and schedules for liquid low-level radioactive waste tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    Not Available

    1992-03-01

    Although the Federal Facility Agreement (FFA) addresses the entire Oak Ridge Reservation, specific requirements are set forth for the liquid low-level radioactive waste (LLLW) storage tanks and their associated piping and equipment, tank systems, at ORNL. The stated objected of the FFA as it relates to these tank systems is to ensure that structural integrity, containment and detection of releases, and source control are maintained pending final remedial action at the site. The FFA requires that leaking LLLW tank systems be immediately removed from service. It also requires the LLLW tank systems that do not meet the design and performance requirements established for secondary containment and leak detection be either upgraded or replaced. The FFA establishes a procedural framework for implementing the environmental laws. For the LLLW tank systems, this framework requires the specified plans and schedules be submitted to EPA and TDEC for approval within 60 days, or in some cases, within 90 days, of the effective date of the agreement.

  7. Federal Facility Agreement plans and schedules for liquid low-level radioactive waste tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

    SciTech Connect

    Not Available

    1992-03-01

    Although the Federal Facility Agreement (FFA) addresses the entire Oak Ridge Reservation, specific requirements are set forth for the liquid low-level radioactive waste (LLLW) storage tanks and their associated piping and equipment, tank systems, at ORNL. The stated objected of the FFA as it relates to these tank systems is to ensure that structural integrity, containment and detection of releases, and source control are maintained pending final remedial action at the site. The FFA requires that leaking LLLW tank systems be immediately removed from service. It also requires the LLLW tank systems that do not meet the design and performance requirements established for secondary containment and leak detection be either upgraded or replaced. The FFA establishes a procedural framework for implementing the environmental laws. For the LLLW tank systems, this framework requires the specified plans and schedules be submitted to EPA and TDEC for approval within 60 days, or in some cases, within 90 days, of the effective date of the agreement.

  8. Tank characterization report for Single-Shell Tank B-111

    SciTech Connect

    Remund, K.M.; Tingey, J.M.; Heasler, P.G.; Toth, J.J.; Ryan, F.M.; Hartley, S.A.; Simpson, D.B.; Simpson, B.C.

    1994-09-01

    Tank 241-B-111 (hereafter referred to as B-111) is a 2,006,300 liter (530,000 gallon) single-shell waste tank located in the 200 East B tank farm at Hanford. Two cores were taken from this tank in 1991 and analysis of the cores was conducted by Battelle`s 325-A Laboratory in 1993. Characterization of the waste in this tank is being done to support Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-44-05. Tank B-111 was constructed in 1943 and put into service in 1945; it is the second tank in a cascade system with Tanks B-110 and B-112. During its process history, B-111 received mostly second-decontamination-cycle waste and fission products waste via the cascade from Tank B-110. This tank was retired from service in 1976, and in 1978 the tank was assumed to have leaked 30,300 liters (8,000 gallons). The tank was interim stabilized and interim isolated in 1985. The tank presently contains approximately 893,400 liters (236,000 gallons) of sludge-like waste and approximately 3,800 liters (1,000 gallons) of supernate. Historically, there are no unreviewed safety issues associated with this tank and none were revealed after reviewing the data from the latest core sampling event in 1991. An extensive set of analytical measurements was performed on the core composites. The major constituents (> 0.5 wt%) measured in the waste are water, sodium, nitrate, phosphate, nitrite, bismuth, iron, sulfate and silicon, ordered from largest concentration to the smallest. The concentrations and inventories of these and other constituents are given. Since Tanks B-110 and B-111 have similar process histories, their sampling results were compared. The results of the chemical analyses have been compared to the dangerous waste codes in the Washington Dangerous Waste Regulations (WAC 173-303). This assessment was conducted by comparing tank analyses against dangerous waste characteristics `D` waste codes; and against state waste codes.

  9. Historical tank content estimate for the southeast quadrant of the Hanford 200 area

    SciTech Connect

    Brevick, C.H.; Stroup, J.L.; Funk, J.W., Fluor Daniel Hanford

    1997-03-14

    The Historical Tank Content Estimate for the Quadrant provides historical information on a tank-by-tank basis of the radioactive mixed wastes stored in the underground single-shell tanks for the Hanford 200 Areas. This report summarized historical information such as waste history, level history, temperature history, riser configuration, tank integrity, and inventory estimates on a tank- by-tank basis. Tank farm aerial photographs and interior tank montages are also provided for each tank. A description of the development of data for the document of the inventory estimates provided by Los Alamos National Laboratory are also given in this report.

  10. IET. Jet fuel tank being lowered into position below grade. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Jet fuel tank being lowered into position below grade. Two tanks already in place. Date: October 18, 1954. INEEL negative no. 12535 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  11. NORTH SIDES OF LIQUID OXYGEN TANKS. Looking southwest along railroad ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    NORTH SIDES OF LIQUID OXYGEN TANKS. Looking southwest along railroad track to AF Plant 72 - Edwards Air Force Base, Air Force Rocket Propulsion Laboratory, Liquid Oxygen & Nitrogen Storage Tank Farm, Intersection of Altair & Jupiter Boulevards, Boron, Kern County, CA

  12. SOUTH SIDE OF TANKS. LOADING DOCK, WITH FIRST AID STATION ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    SOUTH SIDE OF TANKS. LOADING DOCK, WITH FIRST AID STATION IN LEFT FOREGROUND - Edwards Air Force Base, Air Force Rocket Propulsion Laboratory, Liquid Oxygen & Nitrogen Storage Tank Farm, Intersection of Altair & Jupiter Boulevards, Boron, Kern County, CA

  13. OFFICE AND INSTRUMENT ROOM SOUTH OF THE WEST TANK ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    OFFICE AND INSTRUMENT ROOM SOUTH OF THE WEST TANK - Edwards Air Force Base, Air Force Rocket Propulsion Laboratory, Liquid Oxygen & Nitrogen Storage Tank Farm, Intersection of Altair & Jupiter Boulevards, Boron, Kern County, CA

  14. DETAIL, CONTROL BOOTH, RP1 TANK FARM Edwards Air Force ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    DETAIL, CONTROL BOOTH, RP1 TANK FARM - Edwards Air Force Base, Air Force Rocket Propulsion Laboratory, Combined Fuel Storage Tank Farm, Test Area 1-120, north end of Jupiter Boulevard, Boron, Kern County, CA

  15. Tank 241-C-111 vapor sampling and analysis tank characterization report

    SciTech Connect

    Huckaby, J.L.

    1995-05-10

    Tank C-111 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Results presented here represent the best available data on the headspace constituents of Tank C-111. Almost all of the data in this report was obtained from samples collected on September 13, 1994.Data from 2 other sets of samples, collected on August 10, 1993 and June 20, 1994, are in generally good agreement with the more recent data. The tank headspace temperature was determined to be 27 C. Air from the Tank C-111 headspace was withdrawn via a 7.9 m-long heated sampling probe mounted in riser 6, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 50 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, Pacific Northwest Laboratories, and Oregon Graduate Institute of Science and Technology through a contract with Sandia National Laboratories. The 39 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 14 trip blanks provided by the laboratories. Tank C-111 is a single shell tank which received first-cycle decontamination waste from B Plant and was later used as a settling tank.

  16. SRS tank closure. Innovative technology summary report

    SciTech Connect

    Not Available

    1999-08-01

    High-level waste (HLW) tank closure technology is designed to stabilize any remaining radionuclides and hazardous constituents left in a tank after bulk waste removal. Two Savannah River Site (SRS) HLW tanks were closed after cleansing and then filling each tank with three layers of grout. The first layer consists of a chemically reducing grout. The fill material has chemical properties that retard the movement of some radionuclides and chemical constituents. A layer of controlled low-strength material (CLSM), a self-leveling fill material, is placed on top of the reducing grout. CLSM provides sufficient strength to support the overbearing weight. The final layer is a free-flowing, strong grout similar to normal concrete. After the main tank cavity is filled, risers are filled with grout, and all waste transfer piping connected to the tank is isolated. The tank ventilation system is dismantled, and the remaining systems are isolated. Equipment that remains with the tank is filled with grout. The tank and ancillary systems are left in a state requiring only limited surveillance. Administrative procedures are in place to control land use and access. DOE eventually plans to remove all of its HLW storage tanks from service. These tanks are located at SRS, Hanford, and Idaho National Engineering and Environmental Laboratory. Low-activity waste storage tanks at Oak Ridge Reservation are also scheduled for closure.

  17. Dual Tank Fuel System

    DOEpatents

    Wagner, Richard William; Burkhard, James Frank; Dauer, Kenneth John

    1999-11-16

    A dual tank fuel system has primary and secondary fuel tanks, with the primary tank including a filler pipe to receive fuel and a discharge line to deliver fuel to an engine, and with a balance pipe interconnecting the primary tank and the secondary tank. The balance pipe opens close to the bottom of each tank to direct fuel from the primary tank to the secondary tank as the primary tank is filled, and to direct fuel from the secondary tank to the primary tank as fuel is discharged from the primary tank through the discharge line. A vent line has branches connected to each tank to direct fuel vapor from the tanks as the tanks are filled, and to admit air to the tanks as fuel is delivered to the engine.

  18. Function and requirement for a waste disloging and conveyance system for the Idaho National Engineering Laboratory high level liquid waste tanks

    SciTech Connect

    Mullen, O.D.

    1996-09-10

    In 1990 the U.S. Department of Energy (DOE) Office of Technology Development initiated the Light Duty Utility Arm (LDUA) program to support the Consent Order between the State of Idaho, U.S. Department of Energy, and the Environmental Protection Agency that requires ceasing use of the 11 high-level liquid waste (HLLW) storage tanks at the Idaho Chemical Processing Plant (ICPP).

  19. Stabilization of in-tank residual wastes and external-tank soil contamination for the tank focus area, Hanford Tank Initiative: Applications to the AX tank farm

    SciTech Connect

    Becker, D.L.

    1997-11-03

    This report investigates five technical areas for stabilization of decommissioned waste tanks and contaminated soils at the Hanford Site AX Farm. The investigations are part of a preliminary evacuation of end-state options for closure of the AX Tanks. The five technical areas investigated are: (1) emplacement of cementations grouts and/or other materials; (2) injection of chemicals into contaminated soils surrounding tanks (soil mixing); (3) emplacement of grout barriers under and around the tanks; (4) the explicit recognition that natural attenuation processes do occur; and (5) combined geochemical and hydrological modeling. Research topics are identified in support of key areas of technical uncertainty, in each of the five areas. Detailed cost-benefit analyses of the technologies are not provided. This investigation was conducted by Sandia National Laboratories, Albuquerque, New Mexico, during FY 1997 by tank Focus Area (EM-50) funding.

  20. Structural Integrity of Single Shell Tanks at Hanford - 9491

    SciTech Connect

    Rinker, Michael W.; Pilli, Siva Prasad; Karri, Naveen K.; Deibler, John E.; Johnson, Kenneth I.; Holbery, James D.; Mullen, O Dennis; Hurley, David E.

    2009-03-01

    The 149 Single Shell Tanks at the Hanford Site were constructed between the 1940’s and the 1960’s. Many of the tanks are either known or suspected to have leaked in the past. While the free liquids have been removed from the tanks, they still contain significant waste volumes. Recently, the tank farm operations contractor established a Single Shell Tank Integrity Program. Structural integrity is one aspect of the program. The structural analysis of the Single Shell Tanks has several challenging factors. There are several tank sizes and configurations that need to be analyzed. Tank capacities range from fifty-five thousand gallons to one-million gallons. The smallest tank type is approximately twenty feet in diameter, and the three other tank types are all seventy-five feet in diameter. Within each tank type there are varying concrete strengths, types of steel, tank floor arrangements, in-tank hardware, riser sizes and locations, and other appurtenances that need to be addressed. Furthermore, soil properties vary throughout the tank farms. The Pacific Northwest National Laboratory has been conducting preliminary structural analyses of the various single shell tank types to address these parameters. The preliminary analyses will assess which aspects of the tanks will require further detailed analysis. Evaluation criteria to which the tanks will be analyzed are also being developed for the Single Shell Tank Integrity Program. This information will be reviewed by the Single Shell Tank Integrity Expert Panel that has been formed to issue recommendations to the DOE and to the tank farm operations contractor regarding Single Shell Tank Integrity. This paper provides a summary of the preliminary analysis of the single shell tanks, a summary of the recommendations for the detailed analyses, and the proposed evaluation criteria by which the tanks will be judged.

  1. Tank Platoon

    DTIC Science & Technology

    1996-04-03

    mobility , sophisticated communications, enhanced target acquisition, lethal firepower, and effective armor protection. In combi- nation, these factors...including the platoon’s individual tank crews and OPs; the effects of terrain, weather, and movement; and the ranges of all available platoon...dismounted soldiers with automatic weapons. Likewise, enemy activity can range from an entrenched force using prepared fighting positions to a unit

  2. Think Tank.

    ERIC Educational Resources Information Center

    Governick, Heather; Wellington, Thom

    1998-01-01

    Examines the options for upgrading, replacing, and removal or closure of underground storage tanks (UST). Reveals the diverse regulatory control involving USTs, the Environmental Protection Agency's interest in pursuing violators, and stresses the need for administrators to be knowledgeable about state and local agency definitions of regulated…

  3. T-200 series tank concentration predictions

    SciTech Connect

    Engel, D.W.; Remund, K.M.; Chen, G.; Ferryman, T.A.; Daly, D.S.; Hartley, S.A.; Simpson, B.C.

    1997-05-01

    Of the 177 tanks containing nuclear waste at the Hanford site, 68 have not been characterized based on sampling information. It may be possible to characterize 34 of the 68 unsampled tanks by using information from other sources, such as the Tank Characterization Database (TCD) and the Historical Tank Content Estimates (HTCE). This report lists predicted concentrations of 17 analytes along with the associated estimates of uncertainty for the T-200 series tanks (T-201, T-202, T-203, T-204), based on historical data and sample results from tanks other than the T-200 tanks. The main benefits of reduced sampling are reduced cost, reduced time to achieve acceptable characterization, and reduced exposure of sampling personnel. However, in order to characterize a tank on the basis of reducing sampling, the predicted tank averages and the associated uncertainties must be technically credible and useful. The objective of this report is to describe the approach to predict (without a sample) or estimate (from a single sample) the concentrations of the 17 analytes for the T-200 tanks. Sampling of these tanks and laboratory analysis of the samples is currently under way (sampling is scheduled for 03/27/97 through 04/21/97). This report briefly describes the statistical prediction techniques.

  4. Tank 241-U-204 tank characterization plan

    SciTech Connect

    Bell, K.E.

    1995-03-23

    This document is the tank characterization plan for Tank 241-U-204 located in the 200 Area Tank Farm on the Hanford Reservation in Richland, Washington. This plan describes Data Quality Objectives (DQO) and presents historical information and scheduled sampling events for tank 241-U-204.

  5. Tank 241-BY-106 vapor sampling and analysis tank characterization report

    SciTech Connect

    Huckaby, J.L.

    1995-05-10

    Tank BY-106 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Tank BY-106 is on the Ferrocyanide Watch List. Samples were collected from Tank BY-106 using the vapor sampling system (VSS) on July 8, 1994 by WHC Sampling and Mobile Laboratories. The tank headspace temperature was determined to be 27 C. Air from the Tank BY-106 headspace was withdrawn via a heated sampling probe mounted in riser 10B, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 65 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, Pacific Northwest Laboratories, and Oregon Graduate Institute of Science and Technology through a contract with Sandia National Laboratories. The 46 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 10 trip blanks provided by the laboratories.

  6. Tank 241-BY-105 vapor sampling and analysis tank characterization report

    SciTech Connect

    Huckaby, J.L.

    1995-05-10

    Tank BY-105 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Tank BY-105 is on the Ferrocyanide Watch List. Samples were collected from Tank BY-105 using the vapor sampling system (VSS) on July 7, 1994 by WHC Sampling and Mobile Laboratories. The tank headspace temperature was determined to be 26 C. Air from the Tank BY-105 headspace was withdrawn via a heated sampling probe mounted in riser 10A, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 65 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, Pacific Northwest Laboratories, and Oregon Graduate Institute of Science and Technology through a contract with Sandia National Laboratories. The 46 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 10 trip blanks provided by the laboratories.

  7. Feed tank transfer requirements

    SciTech Connect

    Freeman-Pollard, J.R.

    1998-09-16

    This document presents a definition of tank turnover. Also, DOE and PC responsibilities; TWRS DST permitting requirements; TWRS Authorization Basis (AB) requirements; TWRS AP Tank Farm operational requirements; unreviewed safety question (USQ) requirements are presented for two cases (i.e., tank modifications occurring before tank turnover and tank modification occurring after tank turnover). Finally, records and reporting requirements, and documentation which will require revision in support of transferring a DST in AP Tank Farm to a privatization contractor are presented.

  8. Tank Insulation

    NASA Technical Reports Server (NTRS)

    1979-01-01

    For NASA's Apollo program, McDonnell Douglas Astronautics Company, Huntington Beach, California, developed and built the S-IVB, uppermost stage of the three-stage Saturn V moonbooster. An important part of the development task was fabrication of a tank to contain liquid hydrogen fuel for the stage's rocket engine. The liquid hydrogen had to be contained at the supercold temperature of 423 degrees below zero Fahrenheit. The tank had to be perfectly insulated to keep engine or solar heat from reaching the fuel; if the hydrogen were permitted to warm up, it would have boiled off, or converted to gaseous form, reducing the amount of fuel available to the engine. McDonnell Douglas' answer was a supereffective insulation called 3D, which consisted of a one-inch thickness of polyurethane foam reinforced in three dimensions with fiberglass threads. Over a 13-year development and construction period, the company built 30 tanks and never experienced a failure. Now, after years of additional development, an advanced version of 3D is finding application as part of a containment system for transporting Liquefied Natural Gas (LNG) by ship.

  9. Laboratory-Scale Column Testing Using IONSIV IE-911 for Removing Cesium from Acidic Tank Waste Simulant. 2: Determination of Cesium Exchange Capacity and Effective Mass Transfer Coefficient from a 500-cm3 Column Experiement

    SciTech Connect

    T.J. Tranter; R.D. Tillotson; T.A. Todd

    2005-04-01

    A semi-scale column test was performed using a commercial form of crystalline silicotitanate (CST) for removing radio-cesium from a surrogate acidic tank solution, which represents liquid waste stored at the Idaho National Engineering and Environmental Laboratory (INEEL). The engineered form of CST ion exchanger, known as IONSIVtmIE-911 (UOP, Mt. Laurel,NJ, USA), was tested in a 500-cm3 column to obtain a cesium breakthrough curve. The cesium exchange capacity of this column matched that obtained from previous testing with a 15-mc3 column. A numerical algorithm using implicit finite difference approximations was developed to solve the governing mass transport equations for the CST columns. An effective mass transfer coefficient was derived from solving these equations for previously reported 15 cm3 tests. The effective mass transfer coefficient was then used to predict the cesium breakthrough curve for the 500-cm3 column and compared to the experimental data reported in this paper. The calculated breakthrough curve showed excellent agreement with the data from the 500-cm3 column even though the interstitial velocity was a factor of two greater. Thus, this approach should provide a reasonable method for scale up to larger columns for treating actual tank waste.

  10. 49 CFR 172.331 - Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. 172.331 Section 172.331 Transportation Other Regulations... packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. (a) Each...

  11. 49 CFR 172.331 - Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 49 Transportation 2 2012-10-01 2012-10-01 false Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. 172.331 Section 172.331 Transportation Other Regulations... packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. (a) Each...

  12. 49 CFR 172.331 - Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 49 Transportation 2 2014-10-01 2014-10-01 false Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. 172.331 Section 172.331 Transportation Other Regulations... packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. (a) Each...

  13. 49 CFR 172.331 - Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 49 Transportation 2 2013-10-01 2013-10-01 false Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. 172.331 Section 172.331 Transportation Other Regulations... packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. (a) Each...

  14. 49 CFR 172.331 - Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 2 2011-10-01 2011-10-01 false Bulk packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. 172.331 Section 172.331 Transportation Other Regulations... packagings other than portable tanks, cargo tanks, tank cars and multi-unit tank car tanks. (a) Each...

  15. Tank closure reducing grout

    SciTech Connect

    Caldwell, T.B.

    1997-04-18

    A reducing grout has been developed for closing high level waste tanks at the Savannah River Site in Aiken, South Carolina. The grout has a low redox potential, which minimizes the mobility of Sr{sup 90}, the radionuclide with the highest dose potential after closure. The grout also has a high pH which reduces the solubility of the plutonium isotopes. The grout has a high compressive strength and low permeability, which enhances its ability to limit the migration of contaminants after closure. The grout was designed and tested by Construction Technology Laboratories, Inc. Placement methods were developed by the Savannah River Site personnel.

  16. Maintenance Action Work Plan for Waste Area Grouping 1 inactive tanks 3001-B, 3004-B, T-30, and 3013 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

    SciTech Connect

    1995-07-01

    This Maintenance Action Work Plan has been prepared to document the activities and procedures for the remediation of four inactive, low-level radioactive tanks at Waste Area Grouping 1, from the Category D list of tanks in the Federal Facility Agreement for the Oak Ridge Reservation (EPA et al. 1994). The four tanks to remediated are tanks 3001-B, 3004-B, T-30, and 3013. Three of the tanks (3001-B, 3004-B, and T-30) will be physically removed from the ground. Because of logistical issues associted with excavation and site access, the fourth tank (3013) will be grouted in place and permanently closed.

  17. Chemical composition of Hanford Tank SY-102

    SciTech Connect

    Birnbaum, E.; Agnew, S.; Jarvinen, G.; Yarbro, S.

    1993-12-01

    The US Department of Energy established the Tank Waste Remediation System (TWRS) to safely manage and dispose of the radioactive waste, both current and future, stored in double-shell and single-shell tanks at the Hanford sites. One major program element in TWRS is pretreatment which was established to process the waste prior to disposal using the Hanford Waste Vitrification Plant. In support of this program, Los Alamos National Laboratory has developed a conceptual process flow sheet which will remediate the entire contents of a selected double-shelled underground waste tank, including supernatant and sludge, into forms that allow storage and final disposal in a safe, cost-effective and environmentally sound manner. The specific tank selected for remediation is 241-SY-102 located in the 200 West Area. As part of the flow sheet development effort, the composition of the tank was defined and documented. This database was built by examining the history of liquid waste transfers to the tank and by performing careful analysis of all of the analytical data that have been gathered during the tank`s lifetime. In order to more completely understand the variances in analytical results, material and charge balances were done to help define the chemistry of the various components in the tank. This methodology of defining the tank composition and the final results are documented in this report.

  18. Credit BG. View looks south southeast toward tank farm, Rogers ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    Credit BG. View looks south southeast toward tank farm, Rogers Dry Lake is in the background. Each cylindrical tank is labeled for jet fuel grade JP5. Two 2,000 gallon capacity rectangular tanks in midground are fabricated of concrete for storing hydrocarbons; they were constructed in 1993. Structure at extreme right of view is Building 4515, Jet Fuel Testing Laboratory - Edwards Air Force Base, North Base, Aircraft Fuel Tank Farm, Northeast of A Street, Boron, Kern County, CA

  19. RETRIEVAL & TREATMENT OF HANFORD TANK WASTE

    SciTech Connect

    EACKER, J.A.; SPEARS, J.A.; STURGES, M.H.; MAUSS, B.M.

    2006-01-20

    The Hanford Tank Farms contain 53 million gal of radioactive waste accumulated during over 50 years of operations. The waste is stored in 177 single-shell and double-shell tanks in the Hanford 200 Areas. The single-shell tanks were put into operation from the early 1940s through the 1960s with wastes received from several generations of processing facilities for the recovery of plutonium and uranium, and from laboratories and other ancillary facilities. The overall hanford Tank Farm system represents one of the largest nuclear legacies in the world driving towards completion of retrieval and treatment in 2028 and the associated closure activity completion by 2035. Remote operations, significant radiation/contamination levels, limited access, and old facilities are just some of the challenges faced by retrieval and treatment systems. These systems also need to be able to successfully remove 99% or more of the waste, and support waste treatment, and tank closure. The Tank Farm retrieval program has ramped up dramatically in the past three years with design, fabrication, installation, testing, and operations ongoing on over 20 of the 149 single-shell tanks. A variety of technologies are currently being pursued to retrieve different waste types, applications, and to help establish a baseline for recovery/operational efficiencies. The paper/presentation describes the current status of retrieval system design, fabrication, installation, testing, readiness, and operations, including: (1) Saltcake removal progress in Tanks S-102, S-109, and S-112 using saltcake dissolution, modified sluicing, and high pressure water lancing techniques; (2) Sludge vacuum retrieval experience from Tanks C-201, C-202, C-203, and C-204; (3) Modified sluicing experience in Tank C-103; (4) Progress on design and installation of the mobile retrieval system for sludge in potentially leaking single-shell tanks, particularly Tank C-101; and (5) Ongoing installation of various systems in the next

  20. Tank 241-BY-108 vapor sampling and analysis tank characterization report

    SciTech Connect

    Huckaby, J.L.

    1995-05-10

    Tank BY-108 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Tank BY-108 is on the Ferrocyanide Watch List. Samples were collected from Tank BY-108 using the vapor sampling system (VSS) on october 27, 1994 by WHC Sampling and Mobile Laboratories. The tank headspace temperature was determined to be 25.7 C. Air from the Tank BY-108 headspace was withdrawn via a 7.9 m-long heated sampling probe mounted in riser 1, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 50 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, and Pacific Northwest Laboratories. The 40 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 14 trip blanks and 2 field blanks that accompanied the samples.

  1. Tank 241-BY-110 vapor sampling and analysis tank characterization report

    SciTech Connect

    Huckaby, J.L.

    1995-05-10

    Tank BY-110 headspace gas and vapor samples were collected and analyzed to help determine the potential risks to tank farm workers due to fugitive emissions from the tank. Tank BY-110 is on the Ferrocyanide Watch List. Samples were collected from Tank BY-110 using the vapor sampling system (VSS) on November 11, 1994 by WHC Sampling and Mobile Laboratories. The tank headspace temperature was determined to be 27 C. Air from the Tank BY-110 headspace was withdrawn via a 7.9 m-long heated sampling probe mounted in riser 12B, and transferred via heated tubing to the VSS sampling manifold. All heated zones of the VSS were maintained at approximately 50 C. Sampling media were prepared and analyzed by WHC, Oak Ridge National Laboratories, and Pacific Northwest Laboratories. The 40 tank air samples and 2 ambient air control samples collected are listed in Table X-1 by analytical laboratory. Table X-1 also lists the 14 trip blanks and 2 field blanks that accompanied the samples.

  2. VIEW OF PDP TANK TOP (LOWER LEFT) AND RTR/LTR TANK ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    VIEW OF PDP TANK TOP (LOWER LEFT) AND RTR/LTR TANK TOP(LOWER RIGHT), LOOKING SOUTHEAST INTO THE PDP ROOM AT LEVEL 0’. ROLL-UP LOADING DOOR ON RIGHT AND SHEAVE RACKS FOR PDP AND LTR AT TOP - Physics Assembly Laboratory, Area A/M, Savannah River Site, Aiken, Aiken County, SC

  3. FET. Tank Building, TAN631. Elevations, sections, details. Tank pads and ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    FET. Tank Building, TAN-631. Elevations, sections, details. Tank pads and saddles. RAlph M. Parsons 1229-2 ANP/GE-5-631-A-1. Date: March 1957. Approved by INEEL Classification Office for public release. INEEL index code no. 036-0631-00-693-107142 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  4. AX Tank Farm tank removal study

    SciTech Connect

    SKELLY, W.A.

    1999-02-24

    This report examines the feasibility of remediating ancillary equipment associated with the 241-AX Tank Farm at the Hanford Site. Ancillary equipment includes surface structures and equipment, process waste piping, ventilation components, wells, and pits, boxes, sumps, and tanks used to make waste transfers to/from the AX tanks and adjoining tank farms. Two remedial alternatives are considered: (1) excavation and removal of all ancillary equipment items, and (2) in-situ stabilization by grout filling, the 241-AX Tank Farm is being employed as a strawman in engineering studies evaluating clean and landfill closure options for Hanford single-shell tanks. This is one of several reports being prepared for use by the Hanford Tanks Initiative Project to explore potential closure options and to develop retrieval performance evaluation criteria for tank farms.

  5. Tank 241-C-105 tank characterization plan. Revision 1

    SciTech Connect

    Schreiber, R.D.

    1995-01-25

    The Defense Nuclear Facilities Safety Board has advised the DOE to concentrate the near-term sampling and analysis activities on identification and resolution of safety issues. The data quality objective (DQO) process was chosen as a tool to be used to identify the sampling and analytical needs for the resolution of safety issues. Tank C-105 was on the Higher Heat Load Watch List. However, it is presently classified as a non-Watch List low heat load tank and is monitored weekly. This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 222-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples from Tank 241-C-105.

  6. Safety evaluation for packaging transport of LSA-II liquids in MC-312 cargo tanks

    SciTech Connect

    Carlstrom, R.F.

    1996-09-11

    This safety evaluation for packaging authorizes the onsite transfer of bulk LSA-II radioactive liquids in the 222-S Laboratory Cargo Tank and Liquid Effluent Treatment Facility Cargo Tanks (which are U.S. Department of Transportation MC-312 specification cargo tanks) from their operating facilities to tank farm facilities.

  7. Tank 241-U-203: Tank Characterization Plan

    SciTech Connect

    Sathyanarayana, P.

    1995-03-27

    The revised Federal Facility Agreement and Consent Order states that a tank characterization plan will be developed for each double-shell tank and single-shell tank using the data quality objective process. The plans are intended to allow users and regulators to ensure their needs will be met and resources are devoted to gaining only necessary information. This document satisfies that requirement for Tank 241-U-203 sampling activities.

  8. 5. View, oxidizer waste tanks and containment basin in foreground ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    5. View, oxidizer waste tanks and containment basin in foreground with Systems Integration Laboratory (T-28) uphill in background, looking northeast. - Air Force Plant PJKS, Systems Integration Laboratory, Waterton Canyon Road & Colorado Highway 121, Lakewood, Jefferson County, CO

  9. 49 CFR 172.330 - Tank cars and multi-unit tank car tanks.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 49 Transportation 2 2012-10-01 2012-10-01 false Tank cars and multi-unit tank car tanks. 172.330..., TRAINING REQUIREMENTS, AND SECURITY PLANS Marking § 172.330 Tank cars and multi-unit tank car tanks. (a... material— (1) In a tank car unless the following conditions are met: (i) The tank car must be marked...

  10. AX Tank Farm tank removal study

    SciTech Connect

    SKELLY, W.A.

    1998-10-14

    This report considers the feasibility of exposing, demolishing, and removing underground storage tanks from the 241-AX Tank Farm at the Hanford Site. For the study, it was assumed that the tanks would each contain 360 ft{sup 3} of residual waste (corresponding to the one percent residual Inventory target cited in the Tri-Party Agreement) at the time of demolition. The 241-AX Tank Farm is being employed as a ''strawman'' in engineering studies evaluating clean and landfill closure options for Hanford single-shell tank farms. The report is one of several reports being prepared for use by the Hanford Tanks Initiative Project to explore potential closure options and to develop retrieval performance evaluation criteria for tank farms.

  11. Vapor characterization of Tank 241-C-103

    SciTech Connect

    Huckaby, J.L.; Story, M.S.

    1994-06-01

    The Westinghouse Hanford Company Tank Vapor Issue Resolution Program has developed, in cooperation with Northwest Instrument Systems, Inc., Oak Ridge National Laboratory, Oregon Graduate Institute of Science and Technology, Pacific Northwest Laboratory, and Sandia National Laboratory, the equipment and expertise to characterize gases and vapors in the high-level radioactive waste storage tanks at the Hanford Site in south central Washington State. This capability has been demonstrated by the characterization of the tank 241-C-103 headspace. This tank headspace is the first, and for many reasons is expected to be the most problematic, that will be characterized (Osborne 1992). Results from the most recent and comprehensive sampling event, sample job 7B, are presented for the purpose of providing scientific bases for resolution of vapor issues associated with tank 241-C-103. This report is based on the work of Clauss et al. 1994, Jenkins et al. 1994, Ligotke et al. 1994, Mahon et al. 1994, and Rasmussen and Einfeld 1994. No attempt has been made in this report to evaluate the implications of the data presented, such as the potential impact of headspace gases and vapors to tank farm workers health. That and other issues will be addressed elsewhere. Key to the resolution of worker health issues is the quantitation of compounds of toxicological concern. The Toxicology Review Panel, a panel of Pacific Northwest Laboratory experts in various areas, of toxicology, has chosen 19 previously identified compounds as being of potential toxicological concern. During sample job 7B, the sampling and analytical methodology was validated for this preliminary list of compounds of toxicological concern. Validation was performed according to guidance provided by the Tank Vapor Conference Committee, a group of analytical chemists from academic institutions and national laboratories assembled and commissioned by the Tank Vapor Issue Resolution Program.

  12. Stabilization of in-tank residuals and external-tank soil contamination: FY 1997 interim report

    SciTech Connect

    Becker, D.L.

    1997-10-09

    This interim report evaluates various ways to stabilize decommissioned waste tanks and contaminated soils at the AX Tank Farm as part of a preliminary evaluation of end-state options for the Hanford tanks. Five technical areas were considered: (1) emplacement of smart grouts and/or other materials, (2) injection of chemical-getters into contaminated soils surrounding tanks (soil mixing), (3) emplacement of grout barriers under and around the tanks, (4) the use of engineered barriers over the tanks, and (5) the explicit recognition that natural attenuation processes do occur. Research topics are identified in support of key areas of technical uncertainty, in each of the five technical areas. Detailed cost/benefit analyses of the recommended technologies are not provided in this evaluation, performed by Sandia National Laboratories, Albuquerque, New Mexico.

  13. Free convective controls on sequestration of salts into low-permeability strata: Insights from sand tank laboratory experiments and numerical modelling

    NASA Astrophysics Data System (ADS)

    Simmons, C. T.; Post, V.

    2008-12-01

    Vertical reflux of dense brines may occur in hydrogeologic situations including seawater intrusion, transgression-regression cycles, leachate migration from landfills and brine reflux beneath salt lakes. The critical control that geologic heterogeneity plays in the free convective process is still an area which requires significant exploration. To date, no studies have been published that focus on the effect that discrete low- permeability structures have on the free convection process at the scale of individual lenses. The precise local scale solute transport mechanisms that affect solute exchange between the layers of lower and higher permeability have not been reported. Using sand tank experiments and numerical models, we explore local scale solute transport processes associated with free convection in the region both surrounding and within discrete low-permeability strata. Different permeability geometries and contrasts between high- and low- permeability regions are explored. Results show that the free convective processes are inherently complex and not intuitively obvious. In the high-permeability region, salinization was rapid and occurred predominantly by free convective flow around the low-permeability blocks, a process we refer to as 'interlayer convection'. Fresh water originally present within the overall domain considered became trapped both below and within the low-permeability structures. A free convection flow field also became concurrently established within the low-permeability lenses, a process we refer to as 'intralayer convection'. This smaller sublayer scale process is driven by both larger scale interlayer convection and by the buoyancy of the fresh water within the low permeability lenses. It was found that upward vertical flow retards salinization of the lenses as these buoyant freshwater displacements oppose the downward penetration of dissolved salts by diffusion and free convection from above. Due to the presence of vertical upward flow

  14. Environmental, Safety, and Health Plan for the remedial investigation of the liquid low-level waste tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    DeFalco, S.; Kaiser, L. L.; May, L. E.

    1991-09-01

    The Environmental, Safety, and Health (ES H) Plan presents the concepts and methodologies to be used during the Oak Ridge National Laboratory (ORNL) RI/FS project to protect the health and safety of employees, the public, and the environment. The ES H Plan acts as a management extension for ORNL and Energy Systems to direct and control implementation of the project ES H program. This report describes the program philosophy, requirements, quality assurance measures, and methods for applying the ES H program to individual task remedial investigations, project facilities, and other major tasks assigned to the project.

  15. HANFORD TANK CLEANUP UPDATE

    SciTech Connect

    BERRIOCHOA MV

    2011-04-07

    Access to Hanford's single-shell radioactive waste storage tank C-107 was significantly improved when workers completed the cut of a 55-inch diameter hole in the top of the tank. The core and its associated cutting equipment were removed from the tank and encased in a plastic sleeve to prevent any potential spread of contamination. The larger tank opening allows use of a new more efficient robotic arm to complete tank retrieval.

  16. Earthquake response considerations of broad liquid storage tanks

    NASA Astrophysics Data System (ADS)

    Cambra, F. J.

    1982-11-01

    The influences of tank geometry and foundation stiffness variation on the simulated seismic structural response of a model broad tank are discussed. An empirical method for describing tank bottom plate uplift geometry is proposed which recognizes radial catenary force and foundation stiffness. Axial symmetric lift, static tilt and dynamic shaking table tests were performed in the University of California, Berkeley, earthquake simulator laboratory. A structural geometric survey of a 63 ft - 10 inches tall by 289 ft - 6 inches diameter crude oil storage tank was conducted to establish a comparative base by which to evaluate the model tank eccentricities.

  17. Vadose zone characterization project at the Hanford Tank Farms: U Tank Farm Report

    SciTech Connect

    1997-05-01

    The U.S. Department of Energy Grand Junction Office (DOE-GJO) was tasked by the DOE Richland Operations Office (DOE-RL) to perform a baseline characterization of the gamma-ray-emitting radionuclides that are distributed in the vadose zone sediments beneath and around the single-shell tanks (SSTs) at the Hanford Site. The intent of this characterization is to determine the nature and extent of the contamination, to identify contamination sources when possible, and to develop a baseline of the contamination distribution that will permit future data comparisons. This characterization work also allows an initial assessment of the impacts of the vadose zone contamination as required by the Resource Conservation and Recovery Act (RCRA). This characterization project involves acquiring information regarding vadose zone contamination with borehole geophysical logging methods and documenting that information in a series of reports. This information is presently limited to detection of gamma-emitting radionuclides from both natural and man-made sources. Data from boreholes surrounding each tank are compiled into individual Tank Summary Data Reports. The data from each tank in a tank farm are then compiled and summarized in a Tank Farm Report. This document is the Tank Farm Report for the U Tank Farm. Logging operations used high-purity germanium detection systems to acquire laboratory-quality assays of the gamma-emitting radionuclides in the sediments around and below the tanks. These assays were acquired in 59 boreholes that surround the U Tank Farm tanks. Logging of all boreholes was completed in December 1995, and the last Tank Summary Data Report for the U Tank Farm was issued in September 1996.

  18. Stabilization of in-tank residual wastes and external tank soil contamination for the Hanford tank closure program: application to the AX tank farm

    SciTech Connect

    SONNICHSEN, J.C.

    1998-10-12

    Mixed high-level waste is currently stored in underground tanks at the US Department of Energy's (DOE's) Hanford Site. The plan is to retrieve the waste, process the water, and dispose of the waste in a manner that will provide less long-term health risk. The AX Tank Farm has been identified for purposes of demonstration. Not all the waste can be retrieved from the tanks and some waste has leaked from these tanks into the underlying soil. Retrieval of this waste could result in additional leakage. During FY1998, the Sandia National Laboratory was under contract to evaluate concepts for immobilizing the residual waste remaining in tanks and mitigating the migration of contaminants that exist in the soil column. Specifically, the scope of this evaluation included: development of a layered tank fill design for reducing water infiltration; development of in-tank getter technology; mitigation of soil contamination through grouting; sequestering of specific radionuclides in soil; and geochemical and hydrologic modeling of waste-water-soil interactions. A copy of the final report prepared by Sandia National Laboratory is attached.

  19. Parvulescu Revisited: Small Tank Acoustics for Bioacousticians.

    PubMed

    Rogers, Peter H; Hawkins, Anthony D; Popper, Arthur N; Fay, Richard R; Gray, Michael D

    2016-01-01

    Researchers often perform hearing studies on fish in small tanks. The acoustic field in such a tank is considerably different from the acoustic field that occurs in the animal's natural environment. The significance of these differences is magnified by the nature of the fish's auditory system where either acoustic pressure (a scalar), acoustic particle velocity (a vector), or both may serve as the stimulus. It is essential for the underwater acoustician to understand the acoustics of small tanks to be able to carry out valid auditory research in the laboratory and to properly compare and interpret the results of others.

  20. VIEW OF PDP TANK TOP, LEVEL 0’, WITH VERTICAL ELEMENTS ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    VIEW OF PDP TANK TOP, LEVEL 0’, WITH VERTICAL ELEMENTS IN BACKGROUND, LTR TANK TOP ON LEFT, AND SHEAVE RACK ELEMENTS AT TOP, LOOKING NORTH - Physics Assembly Laboratory, Area A/M, Savannah River Site, Aiken, Aiken County, SC

  1. VIEW OF PDP TANK TOP AT LEVEL 0’, WITH VERTICAL ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    VIEW OF PDP TANK TOP AT LEVEL 0’, WITH VERTICAL ELEMENTS IN BACKGROUND AND PART OF SHEAVE RACK ABOVE THE TANK, LOOKING NORTH - Physics Assembly Laboratory, Area A/M, Savannah River Site, Aiken, Aiken County, SC

  2. Sample results from the interim salt disposition program macrobatch 9 tank 21H qualification samples

    SciTech Connect

    Peters, T. B.

    2015-11-01

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 9 for the Interim Salt Disposition Program (ISDP). This document reports characterization data on the samples of Tank 21H.

  3. LPT. EBOR (TAN646) reactor vessel, distribution tank. View of top ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    LPT. EBOR (TAN-646) reactor vessel, distribution tank. View of top of tank, with coolant port below. Photographer: Lowin. Date: January 20, 1965. INEEL negative no. 65-236 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  4. Laboratory-Scale Column Testing Using IONSIV IE-911 for Removing Cesium from Acidic Tank Waste Simulant. 1: Cesium Exchange Capacity of a 15-cm3 Column and Dynamic Stability of the Exchange Media

    SciTech Connect

    T.J. Tranter; R.D. Tillotson; T.A. Todd

    2005-04-01

    Bench-scale column tests were performed using a commercial form of crystalline silicotitanate (CST) for removing radio-cesium from a surrogate acidic tank solution representative of liquid waste stored at the Idaho National Engineering and Environmental Laboratory (INEEL). An engineered form of CST ion exchanger, known as IONSIVtm IE-911 (UOP, Mt Laurel, NJ, USA), was tested in 15 cm3 columns at a flow rate of 5 bed volumes per hour. These experiments showed the ion exchange material to have reasonable selectivity and capacity for removing cesium from the complex chemical matrix of the solution. However, previous testing indicated that partial neutralization of the feed stream was necessary to increase the stability of the ion exchange media. Thus, in these studies, CST degradation was determined as a function of throughput in order to better assess the stability characteristics of the exchanger for potential future waste treatment applications. Results of these tests indicate that the degradation of the CST reaches a maximum very soon after the acidic feed is introduced to the column and then rapidly declines. Total dissolution of bed material did not exceed 3% under the experimental regime used.

  5. Tank characterization report: Tank 241-C-109

    SciTech Connect

    Simpson, B.C.; Borshiem, G.L.; Jensen, L.

    1993-09-01

    Single-shell tank 241-C-109 is a Hanford Site Ferrocyanide Watch List tank that was most recently sampled in September 1992. Analyses of materials obtained from tank 241-C-109 were conducted to support the resolution of the ferrocyanide unreviewed safety question (USQ) and to support Hanford Federal Facility Agreement and consent Order (Tri- Party Agreement) Milestone M-10-00. This report describes this analysis.

  6. Tank Characterization Report for Single Shell Tank 241-C-104

    SciTech Connect

    ADAMS, M.R.

    2000-04-06

    Interprets information about the tank answering a series of six questions covering areas such as information drivers, tank history, tank comparisons, disposal implications, data quality and quantity, and unique aspects of the tank.

  7. Liquid rocket metal tanks and tank components

    NASA Technical Reports Server (NTRS)

    Wagner, W. A.; Keller, R. B. (Editor)

    1974-01-01

    Significant guidelines are presented for the successful design of aerospace tanks and tank components, such as expulsion devices, standpipes, and baffles. The state of the art is reviewed, and the design criteria are presented along with recommended practices. Design monographs are listed.

  8. CHARACTERIZATION OF TANK 19F SAMPLES

    SciTech Connect

    Oji, L.; Diprete, D.; Click, D.

    2009-12-17

    The Savannah River National Laboratory (SRNL) was asked by Liquid Waste Operations to characterize Tank 19F closure samples. Tank 19F slurry samples analyzed included the liquid and solid fractions derived from the slurry materials along with the floor scrape bottom Tank 19F wet solids. These samples were taken from Tank 19F in April 2009 and made available to SRNL in the same month. Because of limited amounts of solids observed in Tank 19F samples, the samples from the north quadrants of the tank were combined into one Tank 19F North Hemisphere sample and similarly the south quadrant samples were combined into one Tank 19F South Hemisphere sample. These samples were delivered to the SRNL shielded cell. The Tank 19F samples were analyzed for radiological, chemical and elemental components. Where analytical methods yielded additional contaminants other than those requested by the customer, these results were also reported. The target detection limits for isotopes analyzed were based on detection values of 1E-04 {micro}Ci/g for most radionuclides and customer desired detection values of 1E-05 {micro}Ci/g for I-129, Pa-231, Np-237, and Ra-226. While many of the target detection limits, as specified in the technical task request and task technical and quality assurance plans were met for the species characterized for Tank 19F, some were not met. In a number of cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. SRNL, in conjunction with the plant customer, reviewed all these cases and determined that the impacts were negligible.

  9. CHARACTERIZATION OF THE TANK 18F SAMPLES

    SciTech Connect

    Oji, L.; Click, D.; Diprete, D.

    2009-12-17

    The Savannah River National Laboratory (SRNL) was asked by Liquid Waste Operations to characterize Tank 18F closure samples. Tank 18F slurry samples analyzed included the liquid and solid fractions derived from the 'as-received' slurry materials along with the floor scrape bottom Tank 18F wet solids. These samples were taken from Tank 18F in March 2009 and made available to SRNL in the same month. Because of limited amounts of solids observed in Tank 18F samples, the samples from the north quadrants of the tank were combined into one North Tank 18F Hemisphere sample and similarly the south quadrant samples were combined into one South Tank 18F Hemisphere sample. These samples were delivered to the SRNL shielded cell. The Tank 18F samples were analyzed for radiological, chemical and elemental components. Where analytical methods yielded additional contaminants other than those requested by the customer, these results were also reported. The target detection limits for isotopes analyzed were 1E-04 {micro}Ci/g for most radionuclides and customer desired detection values of 1E-05 {micro}Ci/g for I-129, Pa-231, Np-237, and Ra-226. While many of the minimum detection limits, as specified in the technical task request and task technical and quality assurance plans were met for the species characterized for Tank 18F, some were not met due to spectral interferences. In a number of cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. SRNL, in conjunction with the plant customer, reviewed all these cases and determined that the impacts were negligible.

  10. Ammonia tank failure

    SciTech Connect

    Sweat, M.E.

    1983-04-01

    An ammonia tank failure at Hawkeye Chemical of Clinton, Iowa is discussed. The tank was a double-wall, 27,000 metric-ton tank built in 1968 and commissioned in December 1969. The paper presented covers the cause of the failure, repair, and procedural changes made to prevent recurrence of the failure. (JMT)

  11. Feed tank transfer requirements

    SciTech Connect

    Freeman-Pollard, J.R.

    1998-09-16

    This document presents a definition of tank turnover; DOE responsibilities; TWRS DST permitting requirements; TWRS Authorization Basis (AB) requirements; TWRS AP Tank Farm operational requirements; unreviewed safety question (USQ) requirements; records and reporting requirements, and documentation which will require revision in support of transferring a DST in AP Tank Farm to a privatization contractor for use during Phase 1B.

  12. 49 CFR 174.63 - Portable tanks, IM portable tanks, IBCs, Large Packagings, cargo tanks, and multi-unit tank car...

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... Packagings, cargo tanks, and multi-unit tank car tanks. 174.63 Section 174.63 Transportation Other....63 Portable tanks, IM portable tanks, IBCs, Large Packagings, cargo tanks, and multi-unit tank car..., Large Packaging, cargo tank, or multi-unit tank car tank) containing a hazardous material in...

  13. 49 CFR 174.63 - Portable tanks, IM portable tanks, IBCs, Large Packagings, cargo tanks, and multi-unit tank car...

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... Packagings, cargo tanks, and multi-unit tank car tanks. 174.63 Section 174.63 Transportation Other....63 Portable tanks, IM portable tanks, IBCs, Large Packagings, cargo tanks, and multi-unit tank car..., Large Packaging, cargo tank, or multi-unit tank car tank) containing a hazardous material in...

  14. 49 CFR 174.63 - Portable tanks, IM portable tanks, IBCs, Large Packagings, cargo tanks, and multi-unit tank car...

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... Packagings, cargo tanks, and multi-unit tank car tanks. 174.63 Section 174.63 Transportation Other....63 Portable tanks, IM portable tanks, IBCs, Large Packagings, cargo tanks, and multi-unit tank car..., Large Packaging, cargo tank, or multi-unit tank car tank) containing a hazardous material in...

  15. 49 CFR 174.63 - Portable tanks, IM portable tanks, IBCs, Large Packagings, cargo tanks, and multi-unit tank car...

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... Packagings, cargo tanks, and multi-unit tank car tanks. 174.63 Section 174.63 Transportation Other....63 Portable tanks, IM portable tanks, IBCs, Large Packagings, cargo tanks, and multi-unit tank car tanks. (a) A carrier may not transport a bulk packaging (e.g., portable tank, IM portable tank,...

  16. Tank 241-B-103 tank characterization plan

    SciTech Connect

    Carpenter, B.C.

    1995-01-23

    The Defense Nuclear Facilities Safety Board (DNFSB) has advised the US Department of Energy (DOE) to concentrate the near-term sampling and analysis activities on identification and resolution of safety issues. The data quality objective (DQO) process was chosen as a tool to be used to identify sampling and analytical needs for the resolution of safety issues. As a result, a revision in the Federal Facility Agreement and Consent Order (Tri-Party Agreement or TPA) milestone M-44-00 has been made, which states that ``A Tank Characterization Plan (TCP) will also be developed for each double-shell tank (DST) and single-shell tank (SST) using the DQO process... Development of TCPs by the DQO process is intended to allow users (e.g., Hanford Facility user groups, regulators) to ensure their needs will be met and that resources are devoted to gaining only necessary information.`` This document satisfies that requirement for Tank 241-B-103 (B-103) sampling activities. Tank B-103 was placed on the Organic Watch List in January 1991 due to review of TRAC data that predicts a TOC content of 3.3 dry weight percent. The tank was classified as an assumed leaker of approximately 30,280 liters (8,000 gallons) in 1978 and declared inactive. Tank B-103 is passively ventilated with interim stabilization and intrusion prevention measures completed in 1985.

  17. Selecting fuel storage tanks

    SciTech Connect

    Doherty, R. )

    1993-07-01

    Until the use of underground storage tanks (USTs) for fuel storage was mandated by the 1970 Uniform Fire Code, above-ground storage tanks (ASTs) were widely used. The tanks were relatively crude by today's standards so the technical superiority and fire protection afforded by use of underground tanks soon made USTs the system of choice for almost all uses. As a result, tens of thousands of tanks have been underground for more than 20 years, and at some point, many of them began leaking. Often, the first sign of these leaks appeared when groundwater became contaminated. The EPA responded to this major environmental problem by strictly regulating the use of below-ground tanks to store flammable liquids. These added regulations have had a severe effect on both service stations and private fueling. The removal of underground tanks and the removal and disposal of any contaminated soil is an extremely expensive proposition. Furthermore, new Uniform Fire Code regulations have added to the costs, imposing requirements for double-walled tanks, corrosion protection, electronic leak monitoring, and annual tank testing. These requirements, plus the financial responsibility requirements the EPA imposed on owners and users of below-ground tanks, led directly to a reconsideration of the use of above-ground tanks for some applications.

  18. SLUDGE BATCH 7 PREPARATION TANK 4 AND 12 CHARACTERIZATION

    SciTech Connect

    Bannochie, C.; Click, D.; Pareizs, J.

    2010-05-21

    Samples of PUREX sludge from Tank 4 and HM sludge from Tank 12 were characterized in preparation for Sludge Batch 7 (SB7) formulation in Tank 51. SRNL analyses on Tank 4 and Tank 12 were requested in separate Technical Assistance Requests (TAR). The Tank 4 samples were pulled on January 19, 2010 following slurry operations by F-Tank Farm. The Tank 12 samples were pulled on February 9, 2010 following slurry operations by H-Tank Farm. At the Savannah River National Laboratory (SRNL), two 200 mL dip samples of Tank 4 and two 200 mL dip samples of Tank 12 were received in the SRNL Shielded Cells. Each tank's samples were composited into clean 500 mL polyethylene storage bottles and weighed. The composited Tank 4 sample was 428.27 g and the composited Tank 12 sample was 502.15 g. As expected there are distinct compositional differences between Tank 4 and Tank 12 sludges. The Tank 12 slurry is much higher in Al, Hg, Mn, and Th, and much lower in Fe, Ni, S, and U than the Tank 4 slurry. The Tank 4 sludge definitely makes the more significant contribution of S to any sludge batch blend. This S, like that observed during SB6 washing, is best monitored by looking at the total S measured by digesting the sample and analyzing by inductively coupled plasma - atomic emission spectroscopy (ICPAES). Alternatively, one can measure the soluble S by ICP-AES and adjust the value upward by approximately 15% to have a pretty good estimate of the total S in the slurry. Soluble sulfate measurements by ion chromatography (IC) will be biased considerably lower than the actual total S, the difference being due to the non-sulfate soluble S and the undissolved S. Tank 12 sludge is enriched in U-235, and hence samples transferred into SRNL from the Tank Farm will need to be placed on the reportable special nuclear material inventory and tracked for total U per SRNL procedure requirements.

  19. VIEW OF PROCESS DEVELOPMENT PILE (PDP) TANK, LOOKING WESTSOUTHWEST, BASEMENT ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    VIEW OF PROCESS DEVELOPMENT PILE (PDP) TANK, LOOKING WEST-SOUTHWEST, BASEMENT LEVEL -15’. EDGE O FRESONANCE TEST REACTOR (RTR), LATER KNOWN AS LATTICE TEST REACTOR (LTR), VISIBLE TO RIGHT OF PDP TANK - Physics Assembly Laboratory, Area A/M, Savannah River Site, Aiken, Aiken County, SC

  20. Unlined Reuseable Filament Wound Composite Cryogenic Tank Testing

    NASA Technical Reports Server (NTRS)

    Murphy, A. W.; Lake, R. E.; Wilkerson, C.

    1999-01-01

    An unlined reusable filament wound composite cryogenic tank was tested at the Marshall Space Flight Center using LH2 cryogen and pressurization to 320 psig. The tank was fabricated by Phillips Laboratory and Wilson Composite Group, Inc., using an EnTec five-axis filament winder and sand mandrels. The material used was IM7/977-2 (graphite/epoxy).

  1. Credit WCT. Photographic copy of photograph, oxidizer and fuel tank ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    Credit WCT. Photographic copy of photograph, oxidizer and fuel tank assembly for engine tests being raised by crane for permanent installation in Test Stand "D" tower. Each tank held 170 gallons of propellants. (JPL negative 384-2029-B, 7 August 1959) - Jet Propulsion Laboratory Edwards Facility, Test Stand D, Edwards Air Force Base, Boron, Kern County, CA

  2. Supporting document for the historical tank content estimate for SY-tank farm

    SciTech Connect

    Brevick, C.H.

    1997-08-12

    The purpose of this historical characterization document is to present the synthesized summaries of the historical records concerning the physical characteristics, radiological, and chemical composition of mixed wastes stored in underground double-shell tanks and the physical condition of these tanks. The double-shell tanks are located on the United States Department of Energy`s Hanford Site, approximately 25 miles northwest or Richland, Washington. The document will be used to assist in characterizing the waste in the tanks in conjunction with the current program of sampling and analyzing the tank wastes. Los Alamos National Laboratory (LANL) developed computer models that used the historical data to attempt to characterize the wastes and to generate estimates of each tank`s inventory. A historical review of the tanks may reveal anomalies or unusual contents that could be critical to characterization and post characterization activities. This document was developed by reviewing the operating plant process histories, waste transfer data, and available physical and chemical data from numerous resources. These resources were generated by numerous contractors from 1945 to the present. Waste characterization, the process of describing the character or quality of a waste, is required by Federal law (Resource Conservation and Recovery Act [RCRA]) and state law (Washington Administrative Code [WAC] 173-303, Dangerous Waste Regulations). Characterizing the waste is necessary to determine methods to safely retrieve, transport, and/or treat the wastes.

  3. 49 CFR 179.400 - General specification applicable to cryogenic liquid tank car tanks.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... liquid tank car tanks. 179.400 Section 179.400 Transportation Other Regulations Relating to... MATERIALS REGULATIONS SPECIFICATIONS FOR TANK CARS Specification for Cryogenic Liquid Tank Car Tanks and... liquid tank car tanks....

  4. Characterization and process technology capabilities for Hanford tank waste disposal

    SciTech Connect

    Buelt, J.L.; Weimer, W.C.; Schrempf, R.E.

    1996-03-01

    The purpose of this document is to describe the Paciflc Northwest National Laboratory`s (the Laboratory) capabilities in characterization and unit process and system testing that are available to support Hanford tank waste processing. This document is organized into two parts. The first section discusses the Laboratory`s extensive experience in solving the difficult problems associated with the characterization of Hanford tank wastes, vitrified radioactive wastes, and other very highly radioactive and/or heterogeneous materials. The second section of this document discusses the Laboratory`s radioactive capabilities and facilities for separations and waste form preparation/testing that can be used to Support Hanford tank waste processing design and operations.

  5. Tank 241-AZ-102 Privatization Push Mode Core Sampling and Analysis Plan

    SciTech Connect

    RASMUSSEN, J.H.

    2000-05-23

    This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for samples obtained from tank 241-AZ-102.

  6. Hanford Tank 241-C-103 Residual Waste Contaminant Release Models and Supporting Data

    SciTech Connect

    Cantrell, Kirk J.; Krupka, Kenneth M.; Deutsch, William J.; Lindberg, Michael J.; Schaef, Herbert T.; Geiszler, Keith N.; Arey, Bruce W.

    2008-01-15

    This report tabulates data generated by laboratory characterization and testing of three samples collected from tank C-103. The data presented here will form the basis for a release model that will be developed for tank C-103. These release models are being developed to support the tank risk assessments performed by CH2M HILL Hanford Group, Inc. for DOE.

  7. 44. ARAIII Fuel oil tank ARA710. Camera facing west. Perimeter ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    44. ARA-III Fuel oil tank ARA-710. Camera facing west. Perimeter fence at left side of view. Gable-roofed building beyond tank on right is ARA-622. Gable-roofed building beyond tank on left is ARA-610. Ineel photo no. 3-16. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  8. Tank 241-BY-109, cores 201 and 203, analytical results for the final report

    SciTech Connect

    Esch, R.A.

    1997-11-20

    This document is the final laboratory report for tank 241-BY-109 push mode core segments collected between June 6, 1997 and June 17, 1997. The segments were subsampled and analyzed in accordance with the Tank Push Mode Core Sampling and Analysis Plan (Bell, 1997), the Tank Safety Screening Data Quality Objective (Dukelow, et al, 1995). The analytical results are included.

  9. RP1 (KEROSENE) STORAGE TANKS ON HILLSIDE EAST OF TEST STAND ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    RP1 (KEROSENE) STORAGE TANKS ON HILLSIDE EAST OF TEST STAND 1-B. THIS TANK FARM SERVES BOTH TEST STANDS 1-A AND 1-B - Edwards Air Force Base, Air Force Rocket Propulsion Laboratory, Combined Fuel Storage Tank Farm, Test Area 1-120, north end of Jupiter Boulevard, Boron, Kern County, CA

  10. 49 CFR 174.63 - Portable tanks, IM portable tanks, IBCs, Large Packagings, cargo tanks, and multi-unit tank car...

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false Portable tanks, IM portable tanks, IBCs, Large Packagings, cargo tanks, and multi-unit tank car tanks. 174.63 Section 174.63 Transportation Other....63 Portable tanks, IM portable tanks, IBCs, Large Packagings, cargo tanks, and multi-unit tank...

  11. RAW WATER STORAGE TANK ON NORTH SIDE OF WATER PUMP ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    RAW WATER STORAGE TANK ON NORTH SIDE OF WATER PUMP HOUSE, TRA-619. INTERIOR. INL NEGATIVE NO. 2489. Unknown Photographer, 6/1951 - Idaho National Engineering Laboratory, Test Reactor Area, Materials & Engineering Test Reactors, Scoville, Butte County, ID

  12. Tank 241-TY-103 rotary core sampling and analysis

    SciTech Connect

    Jo, J.

    1995-10-30

    This Sampling and Analysis Plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for two rotary-mode core samples from tank 241-TY-103

  13. 2. SOUTHEAST SIDE. HIGH PRESSURE HELIUM STORAGE TANKS AT LEFT. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    2. SOUTHEAST SIDE. HIGH PRESSURE HELIUM STORAGE TANKS AT LEFT. - Edwards Air Force Base, Air Force Rocket Propulsion Laboratory, Helium Compression Plant, Test Area 1-115, intersection of Altair & Saturn Boulevards, Boron, Kern County, CA

  14. 20. VIEW OF THE WASTE STORAGE TANKS ASSOCIATED WITH THE ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    20. VIEW OF THE WASTE STORAGE TANKS ASSOCIATED WITH THE PLATING LABORATORY. (11/15/89) - Rocky Flats Plant, Non-Nuclear Production Facility, South of Cottonwood Avenue, west of Seventh Avenue & east of Building 460, Golden, Jefferson County, CO

  15. 19. INTERIOR VIEW INSIDE BUNKER SHOWING NITROGEN TANKS, 'MOBILE AIR ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    19. INTERIOR VIEW INSIDE BUNKER SHOWING NITROGEN TANKS, 'MOBILE AIR MONITOR' EQUIPMENT, MAN. INEL PHOTO NUMBER 65-6183, TAKEN NOVEMBER 10, 1965. - Idaho National Engineering Laboratory, Advanced Reentry Vehicle Fusing System, Scoville, Butte County, ID

  16. VIEW OF TWO HEAVY WATER STORAGE TANKS (BEHIND SUPPORT COLUMNS ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    VIEW OF TWO HEAVY WATER STORAGE TANKS (BEHIND SUPPORT COLUMNS AND STEEL BEAMS), SUB-BASEMENT LEVEL -27’, LOOKING SOUTHWEST - Physics Assembly Laboratory, Area A/M, Savannah River Site, Aiken, Aiken County, SC

  17. VIEW OF PROCESS DEVELOPMENT PILE (PDP) TANK TOP, WITH VERTICAL ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    VIEW OF PROCESS DEVELOPMENT PILE (PDP) TANK TOP, WITH VERTICAL ELEMENTS IN BACKGROUND, LEVEL 0’, LOOKING NORTHWEST - Physics Assembly Laboratory, Area A/M, Savannah River Site, Aiken, Aiken County, SC

  18. VIEW OF SOUTHERNMOST OF TWO HEAVY WATER STORAGE TANKS, LOCATED ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    VIEW OF SOUTHERN-MOST OF TWO HEAVY WATER STORAGE TANKS, LOCATED BEHIND SUPPORT COLUMN, WITH ADJACENT PIPING, LEVEL -27’, LOOKING WEST - Physics Assembly Laboratory, Area A/M, Savannah River Site, Aiken, Aiken County, SC

  19. 16. DETAIL SHOWING LIQUID OXYGEN TANK FOURTEENINCH BALL VALVE. Looking ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    16. DETAIL SHOWING LIQUID OXYGEN TANK FOURTEEN-INCH BALL VALVE. Looking southwest. - Edwards Air Force Base, Air Force Rocket Propulsion Laboratory, Test Stand 1-A, Test Area 1-120, north end of Jupiter Boulevard, Boron, Kern County, CA

  20. Underground storage tank 253-D1U1 Closure Plan

    SciTech Connect

    Mancieri, S.; Giuntoli, N.

    1993-09-01

    This report is a closure plan for a diesel fuel tank at the Lawrence Livermore National Laboratory. Included are maps of the site, work plans, and personnel information regarding training and qualification.

  1. Underground tank vitrification: Engineering-scale test results

    SciTech Connect

    Campbell, B.E.; Timmerman, C.L.; Bonner, W.F.

    1990-06-01

    Contamination associated with underground tanks at US Department of Energy sites and other sites may be effectively remediated by application of in situ vitrification (ISV) technology. In situ vitrification converts contaminated soil and buried wastes such as underground tanks into a glass and crystalline block, similar to obsidian with crystalline phases. A radioactive engineering-scale test performed at Pacific Northwest Laboratory in September 1989 demonstrated the feasibility of using ISV for this application. A 30-cm-diameter (12-in.-diameter) buried steel and concrete tank containing simulated tank sludge was vitrified, producing a solid block. The tank sludge used in the test simulated materials in tanks at Oak Ridge National Laboratory. Hazardous components of the tank sludge were immobilized or removed and captured in the off-gas treatment system. The steel tank was converted to ingots near the bottom of the block and the concrete walls were dissolved into the resulting glass and crystalline block. Although one of the four moving electrodes froze'' in place about halfway into the test, operations were able to continue. The test was successfully completed and all the tank sludge was vitrified. 7 refs., 12 figs., 5 tabs.

  2. 8. View, fuel waste tanks and containment basin associated with ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    8. View, fuel waste tanks and containment basin associated with Components Test Laboratory (T-27) located uphill to the left, looking northwest. - Air Force Plant PJKS, Systems Integration Laboratory, Components Test Laboratory, Waterton Canyon Road & Colorado Highway 121, Lakewood, Jefferson County, CO

  3. 8. Exterior view, showing tank and associated piping adjacent to ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    8. Exterior view, showing tank and associated piping adjacent to Test Cell 6, Systems Integration Laboratory Building (T-28), looking south. - Air Force Plant PJKS, Systems Integration Laboratory, Systems Integration Laboratory Building, Waterton Canyon Road & Colorado Highway 121, Lakewood, Jefferson County, CO

  4. 10. Exterior view, showing the structural details and tanks above ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    10. Exterior view, showing the structural details and tanks above at walk-in entry level (bottom) of Test Cell 7, Systems Integration Laboratory Building (T-28), looking west. - Air Force Plant PJKS, Systems Integration Laboratory, Systems Integration Laboratory Building, Waterton Canyon Road & Colorado Highway 121, Lakewood, Jefferson County, CO

  5. 12. Exterior view, showing tank and piping associated with Test ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    12. Exterior view, showing tank and piping associated with Test Cell 7, Systems Integration Laboratory Building (T-28), looking west. - Air Force Plant PJKS, Systems Integration Laboratory, Systems Integration Laboratory Building, Waterton Canyon Road & Colorado Highway 121, Lakewood, Jefferson County, CO

  6. FRACTIONAL CRYSTALLIZATION FLOWSHEET TESTS WITH ACTUAL TANK WASTE

    SciTech Connect

    HERTING, D.L.

    2007-04-13

    Laboratory-scale flowsheet tests of the fractional crystallization process were conducted with actual tank waste samples in a hot cell at the 2224 Laboratory. The process is designed to separate medium-curie liquid waste into a low-curie stream for feeding to supplemental treatment and a high-curie stream for double-shell tank storage. Separations criteria (for Cesium-137 sulfate and sodium) were exceeded in all three of the flowsheet tests that were performed.

  7. FRACTIONAL CRYSTALLIZATION FLOWSHEET TESTS WITH ACTUAL TANK WASTE

    SciTech Connect

    HERTING, D.L.

    2006-10-18

    Laboratory-scale flowsheet tests of the fractional crystallization process were conducted with actual tank waste samples in a hot cell at the 222-S Laboratory. The process is designed to separate medium-curie liquid waste into a low-curie stream for feeding to supplemental treatment and a high-curie stream for double-shell tank storage. Separations criteria (for Cs-137 sulfate, and sodium) were exceeded in all three of the flowsheet tests that were performed.

  8. Tank overpressure: An uplifting experience

    SciTech Connect

    Morgenegg, E.E.

    1982-05-01

    One of the most common causes of tank damage is uplift. The paper discusses the sources and magnitude of pressure that causes tank uplift, repairs that can be performed on tanks that have lifted, and the prevention of tank uplift. Discussion and examples given are limited to tanks 70 feet or less in diameter.

  9. Analysis of Enriched Uranyl Nitrate in Nested Annular Tank Array

    SciTech Connect

    John D. Bess; James D. Cleaver

    2009-06-01

    Two series of experiments were performed at the Rocky Flats Critical Mass Laboratory during the 1980s using highly enriched (93%) uranyl nitrate solution in annular tanks. [1, 2] Tanks were of typical sizes found in nuclear production plants. Experiments looked at tanks of varying radii in a co-located set of nested tanks, a 1 by 2 array, and a 1 by 3 array. The co-located set of tanks had been analyzed previously [3] as a benchmark for inclusion within the International Handbook of Evaluated Criticality Safety Benchmark Experiments. [4] The current study represents the benchmark analysis of the 1 by 3 array of a series of nested annular tanks. Of the seventeen configurations performed in this set of experiments, twelve were evaluated and nine were judged as acceptable benchmarks.

  10. Fuel Tank Technology

    DTIC Science & Technology

    1989-11-01

    structures b) - Equal thermic inertia c) - Equal fluid volume d) - Equal pressure variation on both wings at the change of the room temperature - This...individual fuel sections. Each fuel section is further ccmpartmentated by metall tank shear walls and tank floors into three individual fuel cells to...plate Dy a stretch forming process, and the metallic tank floors . The air intake segments extend from one bulkhead to the other, thus reducing assembly

  11. Underground petroleum tanks

    SciTech Connect

    Not Available

    1990-07-01

    This book presents the results of a survey of 46 state underground storage tank program officials. The survey covers: Whether petroleum tank insurance (mandated by the EPA) is available in each state and whether category 3 and 4 owners can obtain it; state programs that help owners meet the financial responsibility and/or technical requirements of such insurance; and lending institutions' attitudes towards providing loans to storage tank owners. A survey of the number and terms of insurance policies offered to tank owners is also presented.

  12. Hanford tanks initiative plan

    SciTech Connect

    McKinney, K.E.

    1997-07-01

    Abstract: The Hanford Tanks Initiative (HTI) is a five-year project resulting from the technical and financial partnership of the U.S. Department of Energy`s Office of Waste Management (EM-30) and Office of Science and Technology Development (EM-50). The HTI project accelerates activities to gain key technical, cost performance, and regulatory information on two high-level waste tanks. The HTI will provide a basis for design and regulatory decisions affecting the remainder of the Tank Waste Remediation System`s tank waste retrieval Program.

  13. Characterization of the Basalt of Broken Tank, NM for the 'in situ' Calibration Target for the Alpha-Particle X-ray Spectrometer (APXS) on the Upcoming Mars Science Laboratory (MSL) Rover

    NASA Astrophysics Data System (ADS)

    Burkemper, L.; King, P. L.; Gellert, R.; Spilde, M. N.; Chamberlin, R. M.

    2008-12-01

    The MSL rover mission will launch in Fall 2009. It is equipped with an APXS for analyzing the bulk chemistry of rocks and soils. To monitor the APXS performance in situ on the martian surface over the extended mission, a calibration target will be included on the MSL rover. Engineering constraints led to a 4.2 cm diameter, 3 mm thick, homogeneous rock disc that would survive vibrations during launch. The basalt from Broken Tank, NM was chosen for the flight disc from ~200 volcanic rocks. The basalt is relatively homogeneous, fine- and even-grained, vesicle-free, and extremely dense and hard due to its ophitic texture. Other volcanic rocks - even well characterized samples of BCR - were ruled out due to vesicles, or high contents of glass, phenocrysts, secondary minerals, or fractures. The flight disc was prepared by hand- polishing to a 0.05 micron finish. We obtained scanning electron microscope back-scattered electron maps and X-ray maps (Al, Mg, Ca, Fe, Ti, Na, and K) on the polished, uncoated surface of the target. One pit (~0.03 mm2) and three tiny surface imperfections (<0.04 mm2) were observed on the surface. Electron microprobe analyses on two C-coated thin sections give the following compositions: olivine cores Fa23Fo77 and rims Fa40Fo60; plagioclase cores Ab42An56Or2 and discrete rims Ab62An7Or31; oxides Ilm67Hm33 and also trace chromite, apatite, chlorite, clays and devitrified glass. The NIH software Scion Image was used to determine the modal abundance of each phase in the basalt disk and in two thin sections. Bulk composition was established with multiple XRF laboratory analyses. There is no significant heterogeneity on the scale of the APXS analysis (~1.5 cm). Sulfides were not observed and XRF verified low Ni (<90 ppm) and S (70 ppm), making these elements ideal to monitor any Martian dust build-up during the surface operation. The rock slab is glued into a Ni frame, mounted vertically and accessible with a brush tool. The K- and L- X-ray lines of

  14. Enhanced sludge reduction in septic tanks by increasing temperature.

    PubMed

    Pussayanavin, Tatchai; Koottatep, Thammarat; Eamrat, Rawintra; Polprasert, Chongrak

    2015-01-01

    Septic tanks in most developing countries are constructed without drainage trenches or leaching fields to treat toilet wastewater and /or grey water. Due to the short hydraulic retention time, effluents of these septic tanks are still highly polluted, and there is usually high accumulation of septic tank sludge or septage containing high levels of organics and pathogens that requires frequent desludging and subsequent treatment. This study aimed to reduce sludge accumulation in septic tanks by increasing temperatures of the septic tank content. An experimental study employing two laboratory-scale septic tanks fed with diluted septage and operating at temperatures of 40 and 30°C was conducted. At steady-state conditions, there were more methanogenic activities occurring in the sludge layer of the septic tank operating at the temperature of 40°C, resulting in less total volatile solids (TVS) or sludge accumulation and more methane (CH4) production than in the unit operating at 30°C. Molecular analysis found more abundance and diversity of methanogenic microorganisms in the septic tank sludge operating at 40°C than at 30°C. The reduced TVS accumulation in the 40°C septic tank would lengthen the period of septage removal, resulting in a cost-saving in desluging and septage treatment. Cost-benefit analysis of increasing temperatures in septic tanks was discussed.

  15. TANK 21 AND TANK 24 BLEND AND FEED STUDY: BLENDING TIMES, SETTLING TIMES, AND TRANSFERS

    SciTech Connect

    Lee, S.; Leishear, R.; Poirier, M.

    2012-05-31

    particles have higher density and/or larger size than indicated by previous analysis of SRS sludge and sludge simulants. (5) Tank 21 waste characterization, laboratory settling tests, and additional field turbidity measurements during mixing evolutions are recommended to better understand potential risk for extended (> 60 days) settling times in Tank 21.

  16. 49 CFR 179.401 - Individual specification requirements applicable to inner tanks for cryogenic liquid tank car tanks.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... to inner tanks for cryogenic liquid tank car tanks. 179.401 Section 179.401 Transportation Other..., DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specification for Cryogenic Liquid Tank... requirements applicable to inner tanks for cryogenic liquid tank car tanks....

  17. 49 CFR 179.401 - Individual specification requirements applicable to inner tanks for cryogenic liquid tank car tanks.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... to inner tanks for cryogenic liquid tank car tanks. 179.401 Section 179.401 Transportation Other..., DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specification for Cryogenic Liquid Tank... requirements applicable to inner tanks for cryogenic liquid tank car tanks....

  18. 49 CFR 179.401 - Individual specification requirements applicable to inner tanks for cryogenic liquid tank car tanks.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... to inner tanks for cryogenic liquid tank car tanks. 179.401 Section 179.401 Transportation Other..., DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specification for Cryogenic Liquid Tank... requirements applicable to inner tanks for cryogenic liquid tank car tanks....

  19. 49 CFR 179.401 - Individual specification requirements applicable to inner tanks for cryogenic liquid tank car tanks.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... to inner tanks for cryogenic liquid tank car tanks. 179.401 Section 179.401 Transportation Other..., DEPARTMENT OF TRANSPORTATION (CONTINUED) SPECIFICATIONS FOR TANK CARS Specification for Cryogenic Liquid Tank... requirements applicable to inner tanks for cryogenic liquid tank car tanks....

  20. Tank waste remediation system milestone report magnetic separation of tank waste: Surrogate system separations report

    SciTech Connect

    Avens, L.R.; Worl, L.A.; Schake, A.R.; Padilla, D.D.; de Aguero, K.J.; Prenger, F.C.; Stewart, W.F.; Hill, D.D.

    1994-01-14

    High-level radioactive waste (HLW) has been stored in large underground storage tanks (UST) at the US Department of Energy`s Hanford Site since 1944. More than 253,000 m{sup 3} of waste have been accumulated in 177 tanks. The waste consists of many different chemicals and are in the form of liquids, slurries, salt cakes and sludges. A magnetic separation effort at Los Alamos National Laboratory is funded through the Tank Waste Remediation System (TWRS) to explore the use of high-gradient magnetic separation (HGMS) for tank waste segregation. The concept is to concentrate into a low volume waste stream, all or most of the magnetic components, which include actinide compounds, most of the fission products and precious metals. As a first step in this process investigations were made on surrogate systems. This milestone report discusses the HGMS results on these systems.

  1. Alternative Inspection Methods for Single Shell Tanks

    SciTech Connect

    Peters, Timothy J.; Alzheimer, James M.; Hurley, David E.

    2010-01-19

    This document was prepared to provide evaluations and recommendations regarding nondestructive evaluation methods that might be used to determine cracks and bowing in the ceiling of waste storage tanks on the Hanford site. The goal was to determine cracks as small as 1/16 in. wide in the ceiling, and bowing as small as 0.25 in. This report describes digital video camera methods that can be used to detect a crack in the ceiling of the dome, and methods for determining the surface topography of the ceiling in the waste storage tanks to detect localized movements in the surface. A literature search, combined with laboratory testing, comprised this study.

  2. Underground Tank Management.

    ERIC Educational Resources Information Center

    Bednar, Barbara A.

    1990-01-01

    The harm to human health and our environment caused by leaking underground storage tanks can be devastating. Schools can meet new federal waste management standards by instituting daily inventory monitoring, selecting a reliable volumetric testing company, locating and repairing leaks promptly, and removing and installing tanks appropriately. (MLH)

  3. Oxygen tank assemblies

    NASA Technical Reports Server (NTRS)

    1975-01-01

    Structural design considerations for O2 tank shells and suspension systems of ground based storage and mobile tank systems are outlined. Safety factors, chemical compatibility, liquid slosh strength, and cryogenic temperature properties are summarized. Finally, costs, quality control measures, and long life characteristics are examined.

  4. Model based, sensor-directed remediation of underground storage tanks

    SciTech Connect

    Harrigan, R.W.; Thunborg, S. )

    1990-06-01

    Sensor-rich, intelligent robots that function with respect to models of their environment have significant potential to reduce the time and cost for the cleanup of hazardous waste while increasing operator safety. Sandia National Laboratories (SNL) is performing technology development and experimental investigations into the application of intelligent robot control technology to the problem of cleaning up waste stored in underground tanks. The tasks addressed in the SNL experiments are in situ physical characterizations of underground storage tanks (USTs) as well as the contained waste and the removal of the waste from the tank both for laboratory analysis and as part of the tank cleanup process. Both fully automatic and manual robot control technologies are being developed and demonstrated. The SNL-developed concept of human-assisted computer control will be employed whenever manual control of the robot is required. The UST Robot Technology Development Laboratory (URTDL) consists of a commercial gantry robot modified to allow hybrid force/position control.

  5. Rainwater tank drowning.

    PubMed

    Byard, Roger W

    2008-11-01

    Drowning remains a significant cause of accidental death in young children. The site of drowning varies among communities and is influenced by cultural and geographic factors, including the availability of particular water sources. The drowning deaths of a twin two-year-old brother and sister in a rainwater tank are reported to demonstrate specific issues that may arise. Ladders, vegetation and trellises may provide access to tanks and should be removed. Secure child-proof access points should also be installed, particularly on in-ground tanks (given the ready accessibility of the latter). As there has been a recent trend in Australia to install more domestic rainwater tanks, the number of childhood rainwater tank drownings and near-drownings will need to be monitored by forensic pathologists and child death review committees to ensure that this has not led to the introduction of a new hazard into the home environment.

  6. Tank characterization reference guide

    SciTech Connect

    De Lorenzo, D.S.; DiCenso, A.T.; Hiller, D.B.; Johnson, K.W.; Rutherford, J.H.; Smith, D.J.; Simpson, B.C.

    1994-09-01

    Characterization of the Hanford Site high-level waste storage tanks supports safety issue resolution; operations and maintenance requirements; and retrieval, pretreatment, vitrification, and disposal technology development. Technical, historical, and programmatic information about the waste tanks is often scattered among many sources, if it is documented at all. This Tank Characterization Reference Guide, therefore, serves as a common location for much of the generic tank information that is otherwise contained in many documents. The report is intended to be an introduction to the issues and history surrounding the generation, storage, and management of the liquid process wastes, and a presentation of the sampling, analysis, and modeling activities that support the current waste characterization. This report should provide a basis upon which those unfamiliar with the Hanford Site tank farms can start their research.

  7. Stainless steel tanks

    SciTech Connect

    Hagen, T.

    1995-12-31

    There is currently no recognized code or standard for the design, fabrication and construction of atmospheric and low pressure stainless steel tanks. At the present time these tanks are being designed to individual specifications, manufacturers standards or utilizing other codes and standards that may not be entirely applicable. Recognizing the need, the American Petroleum Institute will be publishing a new appendix to the API STD 650 Standard which will cover stainless steel tanks. The new Appendix was put together by a Task Group of selected individuals from the API Subcommittee of Pressure Vessels and Tanks from the Committee on Refinery Equipment. This paper deals with the development and basis of the new appendix. The new appendix will provide a much needed standard to cover the material, design, fabrication, erection and testing requirements for vertical, cylindrical, austenitic stainless steel aboveground tanks in nonrefrigerated service.

  8. Waste Tank Organic Safety Program: Analytical methods development. Progress report, FY 1994

    SciTech Connect

    Campbell, J.A.; Clauss, S.A.; Grant, K.E.

    1994-09-01

    The objectives of this task are to develop and document extraction and analysis methods for organics in waste tanks, and to extend these methods to the analysis of actual core samples to support the Waste Tank organic Safety Program. This report documents progress at Pacific Northwest Laboratory (a) during FY 1994 on methods development, the analysis of waste from Tank 241-C-103 (Tank C-103) and T-111, and the transfer of documented, developed analytical methods to personnel in the Analytical Chemistry Laboratory (ACL) and 222-S laboratory. This report is intended as an annual report, not a completed work.

  9. 49 CFR 179.201 - Individual specification requirements applicable to non-pressure tank car tanks.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... to non-pressure tank car tanks. 179.201 Section 179.201 Transportation Other Regulations Relating to... MATERIALS REGULATIONS SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes... car tanks....

  10. In-Tank Elutriation Test Report And Independent Assessment

    SciTech Connect

    Burns, H. H.; Adamson, D. J.; Qureshi, Z. H.; Steeper, T. J.

    2011-04-13

    The Department of Energy (DOE) Office of Environmental Management (EM) funded Technology Development and Deployment (TDD) to solve technical problems associated with waste tank closure for sites such as Hanford Site and Savannah River Site (SRS). One of the tasks supported by this funding at Savannah River National Laboratory (SRNL) and Pacific Northwest Laboratory (PNNL) was In-Tank Elutriation. Elutriation is the process whereby physical separation occurs based on particle size and density. This report satisfies the first phase of Task WP_1.3.1.1 In-Tank Elutriation, which is to assess the feasibility of this method of separation in waste tanks at Hanford Site and SRS. This report includes an analysis of scoping tests performed in the Engineering Development Laboratory of SRNL, analysis of Hanford's inadvertent elutriation, the viability of separation methods such as elutriation and hydrocyclones and recommendations for a path forward. This report will demonstrate that the retrieval of Hanford salt waste tank S-112 very successfully decreased the tank's inventories of radionuclides. Analyses of samples collected from the tank showed that concentrations of the major radionuclides Cs-136 and Sr-90 were decreased by factors of 250 and 6 and their total curie tank inventories decreased by factors of 60,000 and 2000. The total tank curie loading decreased from 300,000 Ci to 55 Ci. The remaining heel was nearly all innocuous gibbsite, Al(OH){sub 3}. However, in the process of tank retrieval approximately 85% of the tank gibbsite was also removed. Significant amounts of money and processing time could be saved if more gibbsite could be left in tanks while still removing nearly all of the radionuclides. There were factors which helped to make the elutriation of Tank S-112 successful which would not necessarily be present in all salt tanks. 1. The gibbsite particles in the tank were surprisingly large, as much as 200 {micro}m. The gibbsite crystals had probably grown in

  11. Glass Bubbles Insulation for Liquid Hydrogen Storage Tanks

    NASA Technical Reports Server (NTRS)

    Sass, J. P.; SaintCyr, W. W.; Barrett, T. M.; Baumgartner, R. G.; Lott, J. W.; Fesmire, J. E.

    2009-01-01

    A full-scale field application of glass bubbles insulation has been demonstrated in a 218,000 L liquid hydrogen storage tank. This work is the evolution of extensive materials testing, laboratory scale testing, and system studies leading to the use of glass bubbles insulation as a cost efficient and high performance alternative in cryogenic storage tanks of any size. The tank utilized is part of a rocket propulsion test complex at the NASA Stennis Space Center and is a 1960's vintage spherical double wall tank with an evacuated annulus. The original perlite that was removed from the annulus was in pristine condition and showed no signs of deterioration or compaction. Test results show a significant reduction in liquid hydrogen boiloff when compared to recent baseline data prior to removal of the perlite insulation. The data also validates the previous laboratory scale testing (1000 L) and full-scale numerical modeling (3,200,000 L) of boiloff in spherical cryogenic storage tanks. The performance of the tank will continue to be monitored during operation of the tank over the coming years. KEYWORDS: Glass bubble, perlite, insulation, liquid hydrogen, storage tank.

  12. Tank 241-B-103 headspace gas and vapor characterization: Results for homogeneity samples collected on October 16, 1996. Tank vapor characterization project

    SciTech Connect

    Olsen, K.B.; Pool, K.H.; Evans, J.C.

    1997-06-01

    This report presents the results of analyses of samples taken from the headspace of waste storage tank 241-B-103 (Tank B-103) at the Hanford Site in Washington State. Samples were collected to determine the homogeneity of selected inorganic and organic headspace constituents. Two risers (Riser 2 and Riser 7) were sampled at three different elevations (Bottom, Middle, and Top) within the tank. Tank headspace samples were collected by SGN Eurisys Service Corporation (SESC) and were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL.

  13. Pressurizer tank upper support

    DOEpatents

    Baker, Tod H.; Ott, Howard L.

    1994-01-01

    A pressurizer tank in a pressurized water nuclear reactor is mounted between structural walls of the reactor on a substructure of the reactor, the tank extending upwardly from the substructure. For bearing lateral loads such as seismic shocks, a girder substantially encircles the pressurizer tank at a space above the substructure and is coupled to the structural walls via opposed sway struts. Each sway strut is attached at one end to the girder and at an opposite end to one of the structural walls, and the sway struts are oriented substantially horizontally in pairs aligned substantially along tangents to the wall of the circular tank. Preferably, eight sway struts attach to the girder at 90.degree. intervals. A compartment encloses the pressurizer tank and forms the structural wall. The sway struts attach to corners of the compartment for maximum stiffness and load bearing capacity. A valve support frame carrying the relief/discharge piping and valves of an automatic depressurization arrangement is fixed to the girder, whereby lateral loads on the relief/discharge piping are coupled directly to the compartment rather than through any portion of the pressurizer tank. Thermal insulation for the valve support frame prevents thermal loading of the piping and valves. The girder is shimmed to define a gap for reducing thermal transfer, and the girder is free to move vertically relative to the compartment walls, for accommodating dimensional variation of the pressurizer tank with changes in temperature and pressure.

  14. Pressurizer tank upper support

    DOEpatents

    Baker, T.H.; Ott, H.L.

    1994-01-11

    A pressurizer tank in a pressurized water nuclear reactor is mounted between structural walls of the reactor on a substructure of the reactor, the tank extending upwardly from the substructure. For bearing lateral loads such as seismic shocks, a girder substantially encircles the pressurizer tank at a space above the substructure and is coupled to the structural walls via opposed sway struts. Each sway strut is attached at one end to the girder and at an opposite end to one of the structural walls, and the sway struts are oriented substantially horizontally in pairs aligned substantially along tangents to the wall of the circular tank. Preferably, eight sway struts attach to the girder at 90[degree] intervals. A compartment encloses the pressurizer tank and forms the structural wall. The sway struts attach to corners of the compartment for maximum stiffness and load bearing capacity. A valve support frame carrying the relief/discharge piping and valves of an automatic depressurization arrangement is fixed to the girder, whereby lateral loads on the relief/discharge piping are coupled directly to the compartment rather than through any portion of the pressurizer tank. Thermal insulation for the valve support frame prevents thermal loading of the piping and valves. The girder is shimmed to define a gap for reducing thermal transfer, and the girder is free to move vertically relative to the compartment walls, for accommodating dimensional variation of the pressurizer tank with changes in temperature and pressure. 10 figures.

  15. High organic containing tanks: Assessing the hazard potential

    SciTech Connect

    Hill, R.C.P.; Babad, H.

    1991-09-01

    Eight Hanford Site tanks contain organic chemicals at concentrations believed to be greater than 10 mole percent sodium acetate equivalent mixed with the oxidizing salts sodium nitrate/sodium nitrite. Also, three of the hydrogen and ferrocyanide tanks appear on the organic tank list. Concentrations of organics that may be present in some tanks could cause an exothermic reaction given a sufficient driving force, such as high temperatures. However, the difference between ignition temperatures and actual tank temperatures measured is so large that the probability of such a reaction is considered very low. The consequences of the postulated reaction are about the same as the scenarios for an explosion in a burping'' hydrogen tank. Although work on this issue is just beginning, consideration of hazards associated with heating nitrate-nitrite mixtures containing organic materials is an integral part of both the hydrogen and ferrocyanide tank efforts. High concentrations of organic compounds have been inferred (from tank transfer, flow sheet records, and limited analytical data) in eight single-shell tanks. Many organic chemicals, if present in concentrations above 10 dry weight percent (sodium acetate equivalent), have the potential to react with nitrate-nitrites constituents at temperatures above 200{degree}C (392{degree}F) in an exothermic manner. The concentrations of organic materials in the listed single-shell tanks, and their chemical identity, is not accurately known at present. A tank sampling program has been planned to provide more information on the contents of these tanks and to serve as a basis for laboratory testing and safety evaluations. 2 refs., 1 fig., 2 tabs.

  16. 9. View, oxidizer waste tanks and containment basin associated with ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    9. View, oxidizer waste tanks and containment basin associated with Components Test Laboratory (T-27) located directly uphill, looking north. Located uphill in the upper left portion of the photograph (from right to left) are the Oxidizer Conditioning Structure (T-28D), Long-Term Oxidizer Silo (T-28B), and Systems Integration Laboratory (T-28). - Air Force Plant PJKS, Systems Integration Laboratory, Components Test Laboratory, Waterton Canyon Road & Colorado Highway 121, Lakewood, Jefferson County, CO

  17. Oxygen transfer in circular surface aeration tanks.

    PubMed

    Rao, Achanta Ramakrishna; Patel, Ajey Kumar; Kumar, Bimlesh

    2009-06-01

    Surface aeration systems employed in activated sludge plants are the most energy-intensive units of the plants and typically account for a higher percentage of the treatment facility's total energy use. The geometry of the aeration tank imparts a major effect on the system efficiency. It is said that at optimal geometric conditions, systems exhibits the maximum efficiency. Thus the quantification of the optimal geometric conditions in surface aeration tanks is needed. Optimal geometric conditions are also needed to scale up the laboratory result to the field installation. In the present work, experimental studies have been carried out on baffled and unbaffled circular surface aeration tanks to ascertain the optimal geometric conditions. It is found that no optimal geometric conditions exist for the liquid/water depth in circular surface aeration tanks; however, for design purposes, a standard value has been assumed. Based on the optimal geometric conditions, a scale-up equation has been developed for the baffled circular surface aeration tanks.

  18. Cryogenic-storage-tank support

    NASA Technical Reports Server (NTRS)

    Wisdom, G. H.

    1980-01-01

    Support isolates tank from thermal and mechanical loading by environment. Design uses combination of well-known common mechanisms to isolate tank and allow for tank expansion and contraction due to temperature and pressure changes. Similar support method is used on nitrogen tanks.

  19. 49 CFR 179.401 - Individual specification requirements applicable to inner tanks for cryogenic liquid tank car tanks.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... to inner tanks for cryogenic liquid tank car tanks. 179.401 Section 179.401 Transportation Other... TRANSPORTATION HAZARDOUS MATERIALS REGULATIONS SPECIFICATIONS FOR TANK CARS Specification for Cryogenic Liquid... requirements applicable to inner tanks for cryogenic liquid tank car tanks....

  20. Headspace vapor characterization of Hanford Waste Tank SX-102: Results from samples collected on July 19, 1995. Tank Vapor Characterization Project

    SciTech Connect

    McVeety, B.D.; Evans, J.C.; Clauss, T.W.; Pool, K.H.

    1996-05-01

    This report describes the results of vapor samples taken from the headspace of waste storage tank 241-SX-102 (Tank SX-102) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed under the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5046. Samples were collected by WHC on July 19, 1995, using the vapor sampling system (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  1. Headspace vapor characterization of Hanford Waste Tank 241-T-110: Results from samples collected on August 31, 1995. Tank Vapor Characterization Project

    SciTech Connect

    McVeety, B.D.; Thomas, B.L.; Evans, J.C.

    1996-05-01

    This report describes the results of vapor samples taken from the headspace of waste storage tank 241-T-110 (Tank T-110) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5056. Samples were collected by WHC on August 31, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  2. Headspace vapor characterization of Hanford Waste Tank AX-101: Results from samples collected on June 15, 1995. Tank Vapor Characterization Project

    SciTech Connect

    Pool, K.H.; Clauss, T.W.; Evans, J.C.; McVeety, B.D.

    1996-05-01

    This report describes the results of vapor samples taken from the headspace of waste storage tank 241-AX-101 (Tank AX-101) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) under the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5028. Samples were collected by WHC on June 15, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  3. Headspace vapor characterization of Hanford Waste Tank 241-BX-107: Results from samples collected on November 17, 1995. Tank Vapor Characterization Project

    SciTech Connect

    Evans, J.C.; Thomas, B.L.; Pool, K.H.

    1996-06-01

    This report describes the results of vapor samples taken from the headspace of waste storage tank 241-BX-107 (Tank BX-107) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5080. Samples were collected by WHC on November 17, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  4. Headspace vapor characterization of Hanford Waste Tank 241-S-108: Results from samples collected on December 6, 1995. Tank Vapor Characterization Project

    SciTech Connect

    Thomas, B.L.; Evans, J.C.; McVeety, B.D.

    1996-06-01

    This report describes the results of vapor samples taken from the headspace of waste storage tank 241-S-108 (Tank S-108) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5086. Samples were collected by WHC on December 6, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  5. Headspace vapor characterization of Hanford Waste Tank 241-A-103: Results from samples collected on November 9, 1995. Tank Vapor Characterization Project

    SciTech Connect

    Evans, J.C.; Thomas, B.L.; Pool, K.H.; Olsen, K.B.

    1996-06-01

    This report describes the results of vapor samples taken from the headspace of waste storage tank 241-A-103 (Tank A-103) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5073. Samples were collected by WHC on November 9, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  6. Headspace vapor characterization of Hanford Waste Tank 241-BY-102: Results from samples collected on November 21, 1995. Tank Vapor Characterization Project

    SciTech Connect

    Thomas, B.L.; Evans, J.C.; Pool, K.H.

    1996-06-01

    This report describes the results of vapor samples taken from the headspace of waste storage tank 241-BY-102 (Tank BY-102) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5081. Samples were collected by YMC on November 21, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  7. Headspace vapor characterization of Hanford Waste Tank 241-TX-111: Results from samples collected on October 12, 1995. Tank Vapor Characterization Project

    SciTech Connect

    Pool, K.H.; Clauss, T.W.; Evans, J.C.

    1996-06-01

    This report describes the results of vapor samples taken from the headspace of waste storage tank 241-TX-111 (Tank TX-111) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5069. Samples were collected by WHC on October 12, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  8. Headspace vapor characterization of Hanford Waste Tank 241-SX-109: Results from samples collected on August 1, 1995. Tank Vapor Characterization Project

    SciTech Connect

    Pool, K.H.; Clauss, T.W.; Evans, J.C.

    1996-05-01

    This report describes the results of vapor samples taken from the headspace of waste storage tank 241-SX-109 (Tank SX-109) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5048. Samples were collected by WHC on August 1, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  9. Headspace vapor characterization of Hanford Waste Tank 241-S-112: Results from samples collected on July 11, 1995. Tank Vapor Characterization Project

    SciTech Connect

    Clauss, T.W.; Pool, K.H.; Evans, J.C.

    1996-05-01

    This report describes the results of vapor samples taken from the headspace of waste storage Tank 241-S-112 (Tank S-112) at the Hanford. Pacific Northwest National Laboratory (PNNL) is contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5044. Samples were collected by WHC on July 11, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  10. Headspace vapor characterization of Hanford Waste Tank 241-SX-105: Results from samples collected on July 26, 1995. Tank Vapor Characterization Project

    SciTech Connect

    Pool, K.H.; Clauss, T.W.; Evans, J.C.

    1996-05-01

    This report describes the results of vapor samples taken from the headspace of waste storage tank 241-SX-105 (Tank SX-105) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5047. Samples were collected by WHC on July 26, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  11. Headspace vapor characterization of Hanford Waste Tank 241-SX-104: Results from samples collected on July 25, 1995. Tank Vapor Characterization Project

    SciTech Connect

    Thomas, B.L.; Clauss, T.W.; Evans, J.C.

    1996-05-01

    This report describes the results of vapor samples taken from the headspace of waste storage tank 241-SX-104 (Tank SX-104) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5049. Samples were collected by WHC on July 25, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  12. Headspace vapor characterization of Hanford Waste Tank AX-103: Results from samples collected on June 21, 1995. Tank Vapor Characterization Project

    SciTech Connect

    Ligotke, M.W.; Pool, K.H.; Clauss, T.W.

    1996-05-01

    This report describes the results of vapor samples taken from the headspace of waste storage tank 241-AX-103 (Tank AX-103) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5029. Samples were collected by WHC on June 21, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  13. Headspace vapor charterization of Hanford Waste Tank 241-S-110: Results from samples collected on December 5, 1995. Tank Vapor Characterization Project

    SciTech Connect

    Thomas, B.L.; Evans, J.C.; McVeety, B.D.

    1996-06-01

    This report describes the results of vapor samples taken from the headspace of waste storage tank 241-S-110 (Tank S-110) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was {open_quotes}Vapor Sampling and Analysis Plan{close_quotes}, and the sample job was designated S5085. Samples were collected by WHC on December 5, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace.

  14. 4. View, fuel waste tanks and containment basin in foreground ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    4. View, fuel waste tanks and containment basin in foreground with Systems Integration Laboratory (T-28) uphill in background, looking southeast. At the extreme right is the Long-Term Oxidizer Silo (T-28B) and the Oxidizer Conditioning Structure (T-28D). - Air Force Plant PJKS, Systems Integration Laboratory, Waterton Canyon Road & Colorado Highway 121, Lakewood, Jefferson County, CO

  15. TANK 50 BATCH 0 SALTSTONE FORMULATION CONFIRMATION

    SciTech Connect

    Langton, C.

    2006-06-05

    Savannah River National Laboratory (SRNL) personnel were requested to confirm the Tank 50 Batch 0 grout formulation per Technical Task Request, SSF-TTR-2006-0001 (task 1 of 2) [1]. Earlier Batch 0 formulation testing used a Tank 50 sample collected in September 2005 and is described elsewhere [2]. The current testing was performed using a sample of Tank 50 waste collected in May 2006. This work was performed according to the Technical Task and Quality Assurance Plan (TT/QAP), WSRC-RP-2006-00594 [3]. The salt solution collected from Tank 50 in May 2006 contained approximately 3 weight percent more solids than the sample collected in September 2005. The insoluble solids took longer to settle in the new sample which was interpreted as indicating finer particles in the current sample. The saltstone formulation developed for the September 2005 Tank 50 Batch 0 sample was confirmed for the May 2006 sample with one minor exception. Saltstone prepared with the Tank 50 sample collected in May 2006 required 1.5 times more Daratard 17 set retarding admixture than the saltstone prepared with the September In addition, a sample prepared with lower shear mixing (stirring with a spatula) had a higher plastic viscosity (57 cP) than samples made with higher shear mixing in a blender (23cP). The static gel times of the saltstone slurries made with low shear mixing were also shorter ({approx}32 minutes) than those for comparable samples made in the blender ({approx}47 minutes). The addition of the various waste streams (ETP, HEU-HCAN, and GPE-HCAN) to Tank 50 from September 2005 to May 2006 has increased the amount of set retarder, Daratard 17, required for processing saltstone slurries through the Saltstone facility. If these streams are continued to be added to Tank 50, the quantity of admixtures required to maintain the same processing conditions for the Saltstone facility will probably change and additional testing is recommended to reconfirm the Tank 50 Saltstone formulation.

  16. Underground storage tank 291-D1U1: Closure plan

    SciTech Connect

    Mancieri, S.; Giuntoli, N.

    1993-09-01

    The 291-D1U1 tank system was installed in 1983 on the north side of Building 291. It supplies diesel fuel to the Building 291 emergency generator and air compressor. The emergency generator and air compressor are located southwest and southeast, respectively, of the tank (see Appendix B, Figure 2). The tank system consists of a single-walled, 2,000- gallon, fiberglass tank and a fuel pump system, fill pipe, vent pipe, electrical conduit, and fuel supply and return piping. The area to be excavated is paved with asphalt and concrete. It is not known whether a concrete anchor pad is associated with this tank. Additionally, this closure plan assumes that the diesel tank is below the fill pad. The emergency generator and air compressor for Building 291 and its associated UST, 291-D1U1, are currently in use. The generator and air compressor will be supplied by a temporary above-ground fuel tank prior to the removal of 291-D1U1. An above-ground fuel tank will be installed as a permanent replacement for 291-D1U1. The system was registered with the State Water Resources Control Board on June 27, 1984, as 291-41D and has subsequently been renamed 291-D1U1. Figure 1 (see Appendix B) shows the location of the 291-D1U1 tank system in relation to the Lawrence Livermore National Laboratory (LLNL). Figure 2 (see Appendix B) shows the 291-D1U1 tank system in relation to Building 291. Figure 3 (see Appendix B) shows a plan view of the 291-D1U1 tank system.

  17. Assessment of performing an MST strike in Tank 21H

    SciTech Connect

    Poirier, Michael R.

    2014-09-29

    Previous Savannah River National Laboratory (SRNL) tank mixing studies performed for the Small Column Ion Exchange (SCIX) project have shown that 3 Submersible Mixer Pumps (SMPs) installed in Tank 41 are sufficient to support actinide removal by MST sorption as well as subsequent resuspension and removal of settled solids. Savannah River Remediation (SRR) is pursuing MST addition into Tank 21 as part of the Large Tank Strike (LTS) project. The preliminary scope for LTS involves the use of three standard slurry pumps (installed in N, SE, and SW risers) in a Type IV tank. Due to the differences in tank size, internal interferences, and pump design, a separate mixing evaluation is required to determine if the proposed configuration will allow for MST suspension and strontium and actinide sorption. The author performed the analysis by reviewing drawings for Tank 21 [W231023] and determining the required cleaning radius or zone of influence for the pumps. This requirement was compared with previous pilot-scale MST suspension data collected for SCIX that determined the cleaning radius, or zone of influence, as a function of pump operating parameters. The author also reviewed a previous Tank 50 mixing analysis that examined the ability of standard slurry pumps to suspend sludge particles. Based on a review of the pilot-scale SCIX mixing tests and Tank 50 pump operating experience, three standard slurry pumps should be able to suspend sludge and MST to effectively sorb strontium and actinides onto the MST. Using the SCIX data requires an assumption about the impact of cooling coils on slurry pump mixing. The basis for this assumption is described in this report. Using the Tank 50 operating experience shows three standard slurry pumps should be able to suspend solids if the shear strength of the settled solids is less than 160 Pa. Because Tank 21 does not contain cooling coils, the shear strength could be larger.

  18. Treatment of radioactive wastes from DOE underground storage tanks

    SciTech Connect

    Collins, J.L.; Egan, B.Z.; Spencer, B.B.; Chase, C.W.; Anderson, K.K.; Bell, J.T.

    1994-06-01

    Bench-scale batch tests have been conducted with sludge and supernate tank waste from the Melton Valley Storage Tank (MVST) Facility at Oak Ridge National Laboratory (ORNL) to evaluate separation technology process for use in a comprehensive sludge processing flow sheet as a means of concentrating the radionuclides and reducing the volumes of storage tank waste at national sites for final disposal. This paper discusses the separation of the sludge solids and supernate, the basic washing of the sludge solids, the acidic dissolution of the sludge solids, and the removal of the radionuclides from the supernate.

  19. Investigation of the organic matter in inactive nuclear tank liquids

    SciTech Connect

    Schenley, R.L.; Griest, W.H.

    1990-08-01

    Environmental Protection Agency (EPA) methodology for regulatory organics fails to account for the organic matter that is suggested by total organic carbon (TOC) analysis in the Oak Ridge National Laboratory (ORNL) inactive nuclear waste-tank liquids and sludges. Identification and measurement of the total organics are needed to select appropriate waste treatment technologies. An initial investigation was made of the nature of the organics in several waste-tank liquids. This report details the analysis of ORNL wastes.

  20. Tank Vapor Characterization Project: Vapor space characterization of waste Tank A-101, Results from samples collected on June 8, 1995

    SciTech Connect

    Pool, K.H.; Clauss, T.W.; McVeety, B.D.; Evans, J.C.; Thomas, B.L.; Olsen, K.B.; Fruchter, J.S.; Ligotke, M.W.

    1995-11-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-A-101 (Tank A-101) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank-farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNL. Analyte concentrations were based on analytical results and, where appropriate, sample volumes provided by WHC. A summary of the results is listed in Table 1. Detailed descriptions of the analytical results appear in the text.

  1. Selected in-tank property measurement methods for Hanford Site single-shell tanks

    SciTech Connect

    Morris, K.L.H.; Shattuck, A.F.; Covert, W.A.

    1990-09-01

    The Westinghouse Hanford Company operates the Hanford Site in Washington State for the US Department of Energy. As part of an agreement between the US Department of Energy, the US Environmental Protection Agency, and the Washington State Department of Ecology, Westinghouse Hanford Company has undertaken to clean up the underground tanks located on the Site. These tanks store various radioactive and hazardous wastes produced from chemical processes to refine spent nuclear fuel into defense materials. As part of the cleanup process, equipment must be developed to remove the waste. To design this equipment, the waste must be characterized by its mechanical properties and simulated waste must be made to emulate these properties for equipment testing. A survey of available remote (in-tank) and laboratory techniques was undertaken and the resulting plan to gather all the necessary information involves a three-step approach: laboratory measurements, laboratory measurements on historical synthetic waste mixtures, and in-tank measurements. A list of mechanical properties to be gathered is also included. 3 refs., 3 figs., 2 tabs.

  2. Results of Tank-Leak Detection Demonstration Using Geophysical Techniques at the Hanford Mock Tank Site-Fiscal Year 2001

    SciTech Connect

    Barnett, D BRENT.; Gee, Glendon W.; Sweeney, Mark D.

    2002-03-01

    During July and August of 2001, Pacific Northwest National Laboratory (PNNL), hosted researchers from Lawrence Livermore and Lawrence Berkeley National laboratories, and a private contractor, HydroGEOPHYSICS, Inc., for deployment of the following five geophysical leak-detection technologies at the Hanford Site Mock Tank in a Tank Leak Detection Demonstration (TLDD): (1) Electrical Resistivity Tomography (ERT); (2) Cross-Borehole Electromagnetic Induction (CEMI); (3) High-Resolution Resistivity (HRR); (4) Cross-Borehole Radar (XBR); and (5) Cross-Borehole Seismic Tomography (XBS). Under a ''Tri-party Agreement'' with Federal and state regulators, the U.S. Department of Energy will remove wastes from single-shell tanks (SSTs) and other miscellaneous underground tanks for storage in the double-shell tank system. Waste retrieval methods are being considered that use very little, if any, liquid to dislodge, mobilize, and remove the wastes. As additional assurance of protection of the vadose zone beneath the SSTs, tank wastes and tank conditions may be aggressively monitored during retrieval operations by methods that are deployed outside the SSTs in the vadose zone.

  3. Vacuum Drying of Actual Transuranic Waste from Hanford Tanks

    SciTech Connect

    Tingey, Joel M.

    2004-05-20

    Composites of sludge from Tanks 241-B-203, 241-T-203, 241 T 204, and 241-T-110 at the Hanford Site were prepared at the Hanford 222-S Laboratory from core samples retrieved from these tanks. These tank composites may not be representative of the entire contents of the tank but provide some indication of the properties of the waste within these underground storage tanks. The composite samples were diluted with water at the Radiochemical Processing Laboratory at Pacific Northwest National Laboratory to represent the slurries that are expected to be received from tank retrieval operations and processed to produce a final waste stream. The dilutions were vacuum dried at 60 C and 26 in. of mercury ({approx} 100 torr). Semi-quantitative measurements of stickiness and cohesive strength were made on these dilutions as a function of drying time. Mass loss as a function of drying time and total solids concentration of the initial dilution and at the conclusion of drying were also measured. Visual observations of the sludge were recorded throughout the drying process.

  4. THE RETRIEVAL KNOWLEDGE CENTER EVALUATION OF LOW TANK LEVEL MIXING TECHNOLOGIES FOR DOE HIGH LEVEL WASTE TANK RETRIEVAL 10516

    SciTech Connect

    Fellinger, A.

    2009-12-08

    The Department of Energy (DOE) Complex has over two-hundred underground storage tanks containing over 80-million gallons of legacy waste from the production of nuclear weapons. The majority of the waste is located at four major sites across the nation and is planned for treatment over a period of almost forty years. The DOE Office of Technology Innovation & Development within the Office of Environmental Management (DOE-EM) sponsors technology research and development programs to support processing advancements and technology maturation designed to improve the costs and schedule for disposal of the waste and closure of the tanks. Within the waste processing focus area are numerous technical initiatives which included the development of a suite of waste removal technologies to address the need for proven equipment and techniques to remove high level radioactive wastes from the waste tanks that are now over fifty years old. In an effort to enhance the efficiency of waste retrieval operations, the DOE-EM Office of Technology Innovation & Development funded an effort to improve communications and information sharing between the DOE's major waste tank locations as it relates to retrieval. The task, dubbed the Retrieval Knowledge Center (RKC) was co-lead by the Savannah River National Laboratory (SRNL) and the Pacific Northwest National Laboratory (PNNL) with core team members representing the Oak Ridge and Idaho sites, as well as, site contractors responsible for waste tank operations. One of the greatest challenges to the processing and closure of many of the tanks is complete removal of all tank contents. Sizeable challenges exist for retrieving waste from High Level Waste (HLW) tanks; with complications that are not normally found with tank retrieval in commercial applications. Technologies currently in use for waste retrieval are generally adequate for bulk removal; however, removal of tank heels, the materials settled in the bottom of the tank, using the same

  5. Optical Cryogenic Tank Level Sensor

    NASA Technical Reports Server (NTRS)

    Duffell, Amanda

    2005-01-01

    Cryogenic fluids play an important role in space transportation. Liquid oxygen and hydrogen are vital fuel components for liquid rocket engines. It is also difficult to accurately measure the liquid level in the cryogenic tanks containing the liquids. The current methods use thermocouple rakes, floats, or sonic meters to measure tank level. Thermocouples have problems examining the boundary between the boiling liquid and the gas inside the tanks. They are also slow to respond to temperature changes. Sonic meters need to be mounted inside the tank, but still above the liquid level. This causes problems for full tanks, or tanks that are being rotated to lie on their side.

  6. 131. NORTH PLANT TANK CHEMICAL STORAGE TANKS FROM GB MANUFACTURING ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    131. NORTH PLANT TANK CHEMICAL STORAGE TANKS FROM GB MANUFACTURING PLANT. VIEW TO SOUTHEAST. - Rocky Mountain Arsenal, Bounded by Ninety-sixth Avenue & Fifty-sixth Avenue, Buckley Road, Quebec Street & Colorado Highway 2, Commerce City, Adams County, CO

  7. Material selection for Multi-Function Waste Tank Facility tanks

    SciTech Connect

    Larrick, A.P.; Blackburn, L.D.; Brehm, W.F.; Carlos, W.C.; Hauptmann, J.P.; Danielson, M.J.; Westerman, R.E.; Divine, J.R.; Foster, G.M.

    1995-03-01

    This paper briefly summarizes the history of the materials selection for the US Department of Energy`s high-level waste carbon steel storage tanks. It also provides an evaluation of the materials for the construction of new tanks at the evaluation of the materials for the construction of new tanks at the Multi-Function Waste Tank Facility. The evaluation included a materials matrix that summarized the critical design, fabrication, construction, and corrosion resistance requirements: assessed. each requirement: and cataloged the advantages and disadvantages of each material. This evaluation is based on the mission of the Multi-Function Waste Tank Facility. On the basis of the compositions of the wastes stored in Hanford waste tanks, it is recommended that tanks for the Multi-Function Waste Tank Facility be constructed of ASME SA 515, Grade 70, carbon steel.

  8. Above- and underground storage tanks

    SciTech Connect

    Canning, K.; Kilbourne, A.

    1997-09-01

    Storage tanks are the primary means of storing liquid, fluid and gas products. Federal and state environmental regulations, as well as local building and fire codes, take into account leaks and spills, tank emissions, underground tank seepage and safety issues, and they define standards for tank manufacturers and owners. For specific regulatory information pertaining to your application, contact the local authorities having jurisdiction. Storage tanks listed within this product guide have been classified as underground or aboveground, with subcategories including modular, process and temporary tanks. Tank construction materials include aluminum, carbon steel, concrete, fiberglass-reinforced plastic (FRP) and stainless steel. A variety of accessories, including automatic tank gauging systems, level monitors, leak detectors, overfill protection and tank inspection systems, also are listed. Aboveground storage tanks (ASTs) have less than 10 percent of their tank volume and piping below ground. Available in both vertical and horizontal configurations, they can be either erected in the field or fabricated in a factory. Underground storage tanks (USTs) are primarily used to contain regulated substances; USTs have at least 10% of their tank volume and piping buried belowground. Common UST construction materials include carbon steel, coated steel, cathodically protected steel and FRP. USTs are required to have corrosion protection, spill and overfill prevention and control and release detection in place by December 1998.

  9. Composite overwrapped metallic tanks

    NASA Technical Reports Server (NTRS)

    Caudill, C. L.; Kirlin, R. L.

    1972-01-01

    Work is reported for fabricating and testing the fiberglass overwrapped titanium pressure vessel for cryogenic service. Difficulties encountered in the tank liner fabrication phase involved explosive forming, vacuum annealing, chemical milling and electron beam welding. While each of these processes and the nondestructive test methods employed are normally considered to be individually reliable, the combination of poor material together with fabrication and development reversals prevented the full achievement of the desired end results. Eight tanks plus a prototype and tool proofing article were produced. Six of the vessels failed during the hydrostatic sizing operation. One of the remaining tanks was hydrostatically pressurized to burst and the other was pressurized repeatedly at 75 F from 100 psi to the operating pressure until failure occurred. As a result, it is not possible to draw firm conclusions as to the true value of the design concept due to the problems encountered in the program.

  10. Fireman's Air Tanks

    NASA Technical Reports Server (NTRS)

    1976-01-01

    Together with NASA's Johnson Space Center, A-T-O Inc.'s Scott Aviation has developed light-weight firefighter's air tanks. New backpack system weighs only 20 pounds for 30 minute air supply, 13 pounds less than conventional firefighting tanks. They are pressurized at 4,500 psi, (twice current tanks). Made of aluminum liner wrapped by resin-impregnated glass fibers, eliminating corrosion as well as lightening the load. Redesigned face mask permits better vision. Warning device to tell fireman he is running out of air is personalized so it can't be heard by others reducing confusion in an already hectic environment. Structural Composites Inc., The Boeing Co., and Martin- Marietta Corp. have developed uses for this technology.

  11. The effect of dilution on the gas retention behavior of Tank 241-SY- 103 waste

    SciTech Connect

    Bredt, P.R.; Tingey, S.M.

    1996-01-01

    Twenty-five of the 177 underground waste storage tanks on the Hanford Site have been placed on the Flammable Gas watch list. These 25 tanks, containing high-level waste generated during plutonium and uranium processing, have been identified as potentially capable of accumulating flammable gases above the lower flammability limit (Babad et al. 1991). In the case of Tanks 241-SY-101 and 241-SY-103, it has been proposed that diluting the tank waste may mitigate this hazard (Hudson et al. 1995; Stewart et al. 1994). The effect of dilution on the ability of waste from Tank 241-SY-103 to accumulate gas was studied at Pacific Northwest National Laboratory. A similar study has been completed for waste from Tank 241-SY-101 (Bredt et al. 1995). Because of the additional waste-storage volume available in Tank 241-SY-103 and because the waste is assumed to be similar to that currently in Tank 241-SY-101, Tank 241-SY-103 became the target for a demonstration of passive mitigation through in-tank dilution. In 1994, plans for the in-tank dilution demonstration were deferred pending a decision on whether to pursue dilution as a mitigation strategy. However, because Tank 241-SY-103 is an early retrieval target, determination of how waste properties vary with dilution will still be required.

  12. SLUDGE BATCH 7B QUALIFICATION ACTIVITIES WITH SRS TANK FARM SLUDGE

    SciTech Connect

    Pareizs, J.; Click, D.; Lambert, D.; Reboul, S.

    2011-11-16

    Waste Solidification Engineering (WSE) has requested that characterization and a radioactive demonstration of the next batch of sludge slurry - Sludge Batch 7b (SB7b) - be completed in the Shielded Cells Facility of the Savannah River National Laboratory (SRNL) via a Technical Task Request (TTR). This characterization and demonstration, or sludge batch qualification process, is required prior to transfer of the sludge from Tank 51 to the Defense Waste Processing Facility (DWPF) feed tank (Tank 40). The current WSE practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks. Discharges of nuclear materials from H Canyon are often added to Tank 51 during sludge batch preparation. The sludge is washed and transferred to Tank 40, the current DWPF feed tank. Prior to transfer of Tank 51 to Tank 40, SRNL typically simulates the Tank Farm and DWPF processes with a Tank 51 sample (referred to as the qualification sample). With the tight schedule constraints for SB7b and the potential need for caustic addition to allow for an acceptable glass processing window, the qualification for SB7b was approached differently than past batches. For SB7b, SRNL prepared a Tank 51 and a Tank 40 sample for qualification. SRNL did not receive the qualification sample from Tank 51 nor did it simulate all of the Tank Farm washing and decanting operations. Instead, SRNL prepared a Tank 51 SB7b sample from samples of Tank 7 and Tank 51, along with a wash solution to adjust the supernatant composition to the final SB7b Tank 51 Tank Farm projections. SRNL then prepared a sample to represent SB7b in Tank 40 by combining portions of the SRNL-prepared Tank 51 SB7b sample and a Tank 40 Sludge Batch 7a (SB7a) sample. The blended sample was 71% Tank 40 (SB7a) and 29% Tank 7/Tank 51 on an insoluble solids basis. This sample is referred to as the SB7b Qualification Sample. The blend represented the highest projected Tank 40 heel (as of May 25, 2011), and thus, the highest

  13. 33 CFR 157.15 - Slop tanks in tank vessels.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... (CONTINUED) POLLUTION RULES FOR THE PROTECTION OF THE MARINE ENVIRONMENT RELATING TO TANK VESSELS CARRYING... ballast water containing an oily mixture of 3 percent or more of the oil carrying capacity. Two percent... tank. (2) A new vessel of 70,000 tons DWT or more must have at least two slop tanks. (b) Capacity....

  14. 33 CFR 157.15 - Slop tanks in tank vessels.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... (CONTINUED) POLLUTION RULES FOR THE PROTECTION OF THE MARINE ENVIRONMENT RELATING TO TANK VESSELS CARRYING... ballast water containing an oily mixture of 3 percent or more of the oil carrying capacity. Two percent... tank. (2) A new vessel of 70,000 tons DWT or more must have at least two slop tanks. (b) Capacity....

  15. 33 CFR 157.15 - Slop tanks in tank vessels.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... (CONTINUED) POLLUTION RULES FOR THE PROTECTION OF THE MARINE ENVIRONMENT RELATING TO TANK VESSELS CARRYING... ballast water containing an oily mixture of 3 percent or more of the oil carrying capacity. Two percent... tank. (2) A new vessel of 70,000 tons DWT or more must have at least two slop tanks. (b) Capacity....

  16. 33 CFR 157.15 - Slop tanks in tank vessels.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... (CONTINUED) POLLUTION RULES FOR THE PROTECTION OF THE MARINE ENVIRONMENT RELATING TO TANK VESSELS CARRYING... ballast water containing an oily mixture of 3 percent or more of the oil carrying capacity. Two percent... tank. (2) A new vessel of 70,000 tons DWT or more must have at least two slop tanks. (b) Capacity....

  17. 33 CFR 157.15 - Slop tanks in tank vessels.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... (CONTINUED) POLLUTION RULES FOR THE PROTECTION OF THE MARINE ENVIRONMENT RELATING TO TANK VESSELS CARRYING... ballast water containing an oily mixture of 3 percent or more of the oil carrying capacity. Two percent... tank. (2) A new vessel of 70,000 tons DWT or more must have at least two slop tanks. (b) Capacity....

  18. Tank depletion flow controller

    DOEpatents

    Georgeson, Melvin A.

    1976-10-26

    A flow control system includes two bubbler tubes installed at different levels within a tank containing such as radioactive liquid. As the tank is depleted, a differential pressure transmitter monitors pressure differences imparted by the two bubbler tubes at a remote, shielded location during uniform time intervals. At the end of each uniform interval, balance pots containing a dense liquid are valved together to equalize the pressures. The resulting sawtooth-shaped signal generated by the differential pressure transmitter is compared with a second sawtooth signal representing the desired flow rate during each time interval. Variations in the two signals are employed by a control instrument to regulate flow rate.

  19. TANK SPACE OPTIONS REPORT

    SciTech Connect

    WILLIS WL; AHRENDT MR

    2009-08-11

    Since this report was originally issued in 2001, several options proposed for increasing double-shell tank (DST) storage space were implemented or are in the process of implementation. Changes to the single-shell tank (SST) waste retrieval schedule, completion of DST space saving options, and the DST space saving options in progress have delayed the projected shortfall of DST storage space from the 2007-2011 to the 2018-2025 timeframe (ORP-11242, River Protection Project System Plan). This report reevaluates options from Rev. 0 and includes evaluations of new options for alleviating projected restrictions on SST waste retrieval beginning in 2018 because of the lack of DST storage space.

  20. Enhanced Waste Tank Level Model

    SciTech Connect

    Duignan, M.R.

    1999-06-24

    'With the increased sensitivity of waste-level measurements in the H-Area Tanks and with periods of isolation, when no mass transfer occurred for certain tanks, waste-level changes have been recorded with are unexplained.'

  1. Tanks Emissions for TRI Reporting

    EPA Pesticide Factsheets

    A presentation on overcoming the challenges of TRI reporting for and monitoring the hazardous air emissions from storage tanks, including a discussion on the most accurate and feasible methods of correctly reporting tank emissions to the TRI Program.

  2. Development of simulated tank wastes for the US Department of Energy's Underground Storage Tank Integrated Demonstration

    SciTech Connect

    Elmore, M.R.; Colton, N.G.; Jones, E.O.

    1992-08-01

    The purpose of the Underground Storage Tank Integrated Demonstration (USTID) is to identify and evaluate technologies that may be used to characterize, retrieve, treat, and dispose of hazardous and radioactive wastes contained in tanks on US Department of Energy sites. Simulated wastes are an essential component of the evaluation process because they provide controlled samples for technology assessment, and minimize costs and risks involved when working with radioactive wastes. Pacific Northwest Laboratory has developed a recipe to simulate Hanford single-shell tank, (SST) waste. The recipe is derived from existing process recipes, and elemental concentrations are based on characterization data from 18 SSTs. In this procedure, salt cake and metal oxide/hydroxide sludge are prepared individually, and mixed together at varying ratios depending on the specific tank, waste to be simulated or the test being conducted. Elemental and physical properties of the stimulant are comparable with analyzed tank samples, and chemical speciation in the simulant is being improved as speciation data for actual wastes become available. The nonradioactive chemical waste simulant described here is useful for testing technologies on a small scale.

  3. PROGRESS IN HANFORDS DOUBLE SHELL TANK (DST) INTEGRITY PROJECT

    SciTech Connect

    BERMAN HS

    2008-01-22

    The U.S. Department of Energy's Office of River Protection has an extensive integrity assessment program for the Hanford Site Double-Shell Tank System. The DOE Orders and environmental protection regulations provide the guidelines for the activities used to inspect and maintain 28 double-shell tanks (DSTs), the waste evaporator, and ancillary equipment that compose this system. This program has been reviewed by oversight and regulatory bodies and found to comply with the established guidelines. The basis for the DOE Order 435.1-1 for tank integrity comes from the Tank Structural Integrity Paneled by Brookhaven National Laboratory during the late 1990s. These guidelines established criteria for performing Non-Destructive Examination (NDE), for acceptance of the NDE results, for waste chemistry control, and for monitoring the tanks. The environmental regulations mirror these requirements and allow for the tank integrity program to provide compliant storage of the tanks. Both sets of requirements provide additional guidance for the protection of ancillary equipment. CH2M HILL uses two methods of NDE: visual inspection and Ultrasonic Testing (UT). The visual inspection program examines the primary tank and secondary liner of the DST. The primary tank is examined both on the interior surface above the waste in the tank and on the exterior surface facing the annulus of the DST. The interior surface of the tank liner is examined at the same time as the outer surface of the primary tank. The UT program examines representative areas of the primary tank and secondary liner by deploying equipment in the annulus of the tank. Both programs have led to the development of new equipment for remote inspection of the tanks. Compact camera and enhanced lighting systems have been designed and deployed through narrow access ports (called risers) into the tanks. The UT program has designed two generations of crawlers and equipment for deployment through risers into the thermally hot and

  4. Progress in Hanford's Double-Shell Tank Integrity Project

    SciTech Connect

    Bryson, D.C.; Washenfelder, D.J.; Boomer, K.D.

    2008-07-01

    The U.S. Department of Energy's Office of River Protection has an extensive integrity assessment program for the Hanford Site Double-Shell Tank System. The DOE Orders and environmental protection regulations provide the guidelines for the activities used to inspect and maintain 28 double-shell tanks (DSTs), the waste evaporator, and ancillary equipment that compose this system. This program has been reviewed by oversight and regulatory bodies and found to comply with the established guidelines. The basis for the DOE Order 435.1-1 for tank integrity comes from the Tank Structural Integrity Panel led by Brookhaven National Laboratory during the late 1990's. These guidelines established criteria for performing Non-Destructive Examination (NDE), for acceptance of the NDE results, for waste chemistry control, and for monitoring the tanks. The environmental regulations mirror these requirements and allow for the tank integrity program to provide compliant storage of the tanks. Both sets of requirements provide additional guidance for the protection of ancillary equipment. CH2M HILL uses two methods of NDE: visual inspection and Ultrasonic Testing (UT). The visual inspection program examines the primary tank and secondary liner of the DST. The primary tank is examined both on the interior surface above the waste in the tank and on the exterior surface facing the annulus of the DST. The interior surface of the tank liner is examined at the same time as the outer surface of the primary tank. The UT program examines representative areas of the primary tank and secondary liner by deploying equipment in the annulus of the tank. Both programs have led to the development of new equipment for remote inspection of the tanks. Compact camera and enhanced lighting systems have been designed and deployed through narrow access ports (called risers) into the tanks. The UT program has designed two generations of crawlers and equipment for deployment through risers into the thermally hot

  5. VOLUMETRIC TANK TESTING: AN OVERVIEW

    EPA Science Inventory

    This report summarizes the technical findings of an EPA study on volumetric tank testing. It describes the results of the EPA study, which evaluated the viability of volumetric tank tests as a means of detecting leaks in underground storage tanks. It explains the accuracy requi...

  6. VOLUMETRIC TANK TESTING: AN OVERVIEW

    EPA Science Inventory

    This report summarizes the technical findings of an EPA study on volumetric tank testing. The results of this study, which evaluated the viability of volumetric tank tests as a means of detecting leaks in underground storage tanks, are described. Also, the accuracy requirements s...

  7. Plating Tank Control Software

    SciTech Connect

    Krafcik, John

    1998-03-01

    The Plating Tank Control Software is a graphical user interface that controls and records plating process conditions for plating in high aspect ratio channels that require use of low current and long times. The software is written for a Pentium II PC with an 8 channel data acquisition card, and the necessary shunt resistors for measuring currents in the millampere range.

  8. Hybrid Tank Technology

    NASA Technical Reports Server (NTRS)

    2004-01-01

    Researchers have accomplished great advances in pressure vessel technology by applying high-performance composite materials as an over-wrap to metal-lined pressure vessels. These composite over-wrapped pressure vessels (COPVs) are used in many areas, from air tanks for firefighters and compressed natural gas tanks for automobiles, to pressurant tanks for aerospace launch vehicles and propellant tanks for satellites and deep-space exploration vehicles. NASA and commercial industry are continually striving to find new ways to make high-performance pressure vessels safer and more reliable. While COPVs are much lighter than all-metal pressure vessels, the composite material, typically graphite fibers with an epoxy matrix resin, is vulnerable to impact damage. Carbon fiber is most frequently used for the high-performance COPV applications because of its high strength-to-weight characteristics. Other fibers have been used, but with limitations. For example, fiberglass is inexpensive but much heavier than carbon. Aramid fibers are impact resistant but have less strength than carbon and their performance tends to deteriorate.

  9. Friction Stir Welded Thin Wall Cryogenic Tank Skins

    NASA Astrophysics Data System (ADS)

    Potter, David M.; Takeshita, Jennifer A.; Holguin, Michael J.

    2007-01-01

    A cryogenic propellant tank is the common element of trans-planetary transportation systems, in-space storage depots, lunar landers, in-space habitats/laboratories, ascent/descent, and launch vehicles. Lockheed Martin's (LM) cryogenic tank approach integrates Friction Stir Welding (FSW) with thin-gage aluminum monocoque structural design, common spin formed FSW domes and variable tank lengths to tailor the cryogenic tank from smaller stages, such as landers or ascent/descent stages, to very large on-orbit or In Space Resource Utilization (ISRU) storage systems. Thin gage corrosion resistant steel (CRES) construction combined with normal fusion welding as used on LM's Centaur has already been demonstrated to provide the highest cryogenic tank mass fraction (~.90) for large scale, cryogenic propellant storage. However, current fusion welding technology is limited by the alloys that are considered weldable and typically achieves only 50% of the parent material ultimate strength at the weld joint. Preliminary LM technology development indicates that in certain aluminum alloys, the FSW joint retains up to 100% of the parent material ultimate strength at LH2 temperatures. Combining FSW and aluminum monocoque tank design would create a large scale cryogenic tank with a mass fraction in excess of the current industry standard and therefore is ideal for affordable, reliable, high capacity propellant storage required for all facets of space exploration.

  10. Physical Property and Rheological Testing of Actual Transuranic Waste from Hanford Single-Shell Tanks

    SciTech Connect

    Tingey, Joel M. ); Gao, Johnway ); Delegard, Calvin H. ); Bagaasen, Larry M. ); Wells, Beric E. )

    2003-08-25

    Composites of sludge from Hanford tanks 241-B-203 (B-203), 241-T-203 (T-203), 241-T-204 (T-204), and 241-T-110 (T-110) were prepared at the Hanford 222-S Laboratory and transferred to the Radiochemical Processing Laboratory at the Pacific Northwest National Laboratory (PNNL) for measurement of the composites' physical properties. These tank composites were prepared from core samples retieved from these tanks. These core samples may not be representative of the entire contents of the tank but provide some indication of the properties of the waste in these underground storage tanks. Dilutions in water were prepared from the composite samples. The measurements included paint filter tests, viscosity, shear strength, settling and centrifuging behavior, a qualitative test of stickiness, total solids concentration, and extrusion tests to estimate shear strength.

  11. 49 CFR 179.500 - Specification DOT-107A * * * * seamless steel tank car tanks.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 49 Transportation 3 2013-10-01 2013-10-01 false Specification DOT-107A * * * * seamless steel tank...) SPECIFICATIONS FOR TANK CARS Specification for Cryogenic Liquid Tank Car Tanks and Seamless Steel Tanks (Classes DOT-113 and 107A) § 179.500 Specification DOT-107A * * * * seamless steel tank car tanks....

  12. 49 CFR 179.500 - Specification DOT-107A * * * * seamless steel tank car tanks.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 49 Transportation 3 2014-10-01 2014-10-01 false Specification DOT-107A * * * * seamless steel tank...) SPECIFICATIONS FOR TANK CARS Specification for Cryogenic Liquid Tank Car Tanks and Seamless Steel Tanks (Classes DOT-113 and 107A) § 179.500 Specification DOT-107A * * * * seamless steel tank car tanks....

  13. 49 CFR 179.500 - Specification DOT-107A * * * * seamless steel tank car tanks.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false Specification DOT-107A * * * * seamless steel tank... REGULATIONS SPECIFICATIONS FOR TANK CARS Specification for Cryogenic Liquid Tank Car Tanks and Seamless Steel Tanks (Classes DOT-113 and 107A) § 179.500 Specification DOT-107A * * * * seamless steel tank car tanks....

  14. 49 CFR 179.500 - Specification DOT-107A * * * * seamless steel tank car tanks.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 49 Transportation 3 2012-10-01 2012-10-01 false Specification DOT-107A * * * * seamless steel tank...) SPECIFICATIONS FOR TANK CARS Specification for Cryogenic Liquid Tank Car Tanks and Seamless Steel Tanks (Classes DOT-113 and 107A) § 179.500 Specification DOT-107A * * * * seamless steel tank car tanks....

  15. 49 CFR 179.500 - Specification DOT-107A * * * * seamless steel tank car tanks.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 3 2011-10-01 2011-10-01 false Specification DOT-107A * * * * seamless steel tank...) SPECIFICATIONS FOR TANK CARS Specification for Cryogenic Liquid Tank Car Tanks and Seamless Steel Tanks (Classes DOT-113 and 107A) § 179.500 Specification DOT-107A * * * * seamless steel tank car tanks....

  16. 49 CFR 179.301 - Individual specification requirements for multi-unit tank car tanks.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ...-unit tank car tanks. 179.301 Section 179.301 Transportation Other Regulations Relating to... (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Multi-Unit Tank Car Tanks (Classes DOT-106A and 110AW) § 179.301 Individual specification requirements for multi-unit tank car tanks. (a) In addition...

  17. 49 CFR 179.201 - Individual specification requirements applicable to non-pressure tank car tanks.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... to non-pressure tank car tanks. 179.201 Section 179.201 Transportation Other Regulations Relating to... (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.201 Individual specification requirements applicable to non-pressure tank car tanks....

  18. 49 CFR 179.201 - Individual specification requirements applicable to non-pressure tank car tanks.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... to non-pressure tank car tanks. 179.201 Section 179.201 Transportation Other Regulations Relating to... (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.201 Individual specification requirements applicable to non-pressure tank car tanks....

  19. 49 CFR 179.301 - Individual specification requirements for multi-unit tank car tanks.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ...-unit tank car tanks. 179.301 Section 179.301 Transportation Other Regulations Relating to... (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Multi-Unit Tank Car Tanks (Classes DOT-106A and 110AW) § 179.301 Individual specification requirements for multi-unit tank car tanks. (a) In addition...

  20. 49 CFR 179.400 - General specification applicable to cryogenic liquid tank car tanks.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... liquid tank car tanks. 179.400 Section 179.400 Transportation Other Regulations Relating to... (CONTINUED) SPECIFICATIONS FOR TANK CARS Specification for Cryogenic Liquid Tank Car Tanks and Seamless Steel Tanks (Classes DOT-113 and 107A) § 179.400 General specification applicable to cryogenic liquid tank...

  1. 49 CFR 179.400 - General specification applicable to cryogenic liquid tank car tanks.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... liquid tank car tanks. 179.400 Section 179.400 Transportation Other Regulations Relating to... (CONTINUED) SPECIFICATIONS FOR TANK CARS Specification for Cryogenic Liquid Tank Car Tanks and Seamless Steel Tanks (Classes DOT-113 and 107A) § 179.400 General specification applicable to cryogenic liquid tank...

  2. 49 CFR 179.101 - Individual specification requirements applicable to pressure tank car tanks.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... to pressure tank car tanks. 179.101 Section 179.101 Transportation Other Regulations Relating to... MATERIALS REGULATIONS SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT... tank car tanks. Editorial Note: At 66 FR 45186, Aug. 28, 2001, an amendment published amending a...

  3. 49 CFR 179.301 - Individual specification requirements for multi-unit tank car tanks.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ...-unit tank car tanks. 179.301 Section 179.301 Transportation Other Regulations Relating to... (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Multi-Unit Tank Car Tanks (Classes DOT-106A and 110AW) § 179.301 Individual specification requirements for multi-unit tank car tanks. (a) In addition...

  4. 49 CFR 179.201 - Individual specification requirements applicable to non-pressure tank car tanks.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... to non-pressure tank car tanks. 179.201 Section 179.201 Transportation Other Regulations Relating to... (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Non-Pressure Tank Car Tanks (Classes DOT-111AW and 115AW) § 179.201 Individual specification requirements applicable to non-pressure tank car tanks....

  5. 49 CFR 179.400 - General specification applicable to cryogenic liquid tank car tanks.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... liquid tank car tanks. 179.400 Section 179.400 Transportation Other Regulations Relating to... (CONTINUED) SPECIFICATIONS FOR TANK CARS Specification for Cryogenic Liquid Tank Car Tanks and Seamless Steel Tanks (Classes DOT-113 and 107A) § 179.400 General specification applicable to cryogenic liquid tank...

  6. 49 CFR 179.301 - Individual specification requirements for multi-unit tank car tanks.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ...-unit tank car tanks. 179.301 Section 179.301 Transportation Other Regulations Relating to... MATERIALS REGULATIONS SPECIFICATIONS FOR TANK CARS Specifications for Multi-Unit Tank Car Tanks (Classes DOT-106A and 110AW) § 179.301 Individual specification requirements for multi-unit tank car tanks. (a)...

  7. FY2003 Visual examination of In Tank and Tank annuli at 241-SY tank farm

    SciTech Connect

    AFTANAS, B.L.

    2003-07-08

    This report documents the completion of the FY 2003 in-tank and annulus video inspections for the 241-SY tank farms. Representative photos of observed anomalies, water-streaks, corrosion deposits, pitting, and in-tank strains on the 241-SY-101, 102 & 103

  8. POTENTIAL IMPACT OF BLENDING RESIDUAL SOLIDS FROM TANKS 18/19 MOUNDS WITH TANK 7 OPERATIONS

    SciTech Connect

    Eibling, R; Erich Hansen, E; Bradley Pickenheim, B

    2007-03-29

    High level waste tanks 18F and 19F have residual mounds of waste which may require removal before the tanks can be closed. Conventional slurry pump technology, previously used for waste removal and tank cleaning, has been incapable of removing theses mounds from tanks 18F and 19F. A mechanical cleaning method has been identified that is potentially capable of removing and transferring the mound material to tank 7F for incorporation in a sludge batch for eventual disposal in high level waste glass by the Defense Waste Processing Facility. The Savannah River National Laboratory has been requested to evaluate whether the material transferred from tanks 18F/19F by the mechanical cleaning technology can later be suspended in Tank 7F by conventional slurry pumps after mixing with high level waste sludge. The proposed mechanical cleaning process for removing the waste mounds from tanks 18 and 19 may utilize a high pressure water jet-eductor that creates a vacuum to mobilize solids. The high pressure jet is also used to transport the suspended solids. The jet-eductor system will be mounted on a mechanical crawler for movement around the bottom of tanks 18 and 19. Based on physical chemical property testing of the jet-eductor system processed IE-95 zeolite and size-reduced IE-95 zeolite, the following conclusions were made: (1) The jet-eductor system processed zeolite has a mean and median particle size (volume basis) of 115.4 and 43.3 microns in water. Preferential settling of these large particles is likely. (2) The jet-eductor system processed zeolite rapidly generates settled solid yield stresses in excess of 11,000 Pascals in caustic supernates and will not be easily retrieved from Tank 7 with the existing slurry pump technology. (3) Settled size-reduced IE-95 zeolite (less than 38 microns) in caustic supernate does not generate yield stresses in excess of 600 Pascals in less than 30 days. (4) Preferential settling of size-reduced zeolite is a function of the amount of

  9. In-tank precipitation facility (ITP) and H-Tank Farm (HTF) geotechnical report, WSRC-TR-95-0057, Revision 0, Volume 5

    SciTech Connect

    1995-11-01

    A geotechnical study has been completed in H-Area for the In-Tank Precipitation Facility (ITP) and the balance of the H-Area Tank Farm (HTF) at the Savannah River Site (SRS) in South Carolina. The study consisted of subsurface field exploration, field and laboratory testing, and engineering analyses. The purpose of these investigations is to evaluate the overall stability of the H-Area tanks under static and dynamic conditions. The objectives of the study are to define the site-specific geological conditions at ITP and HTF, obtain engineering properties for the assessment of the stability of the native soils and embankment under static and dynamic loads (i.e., slope stability, liquefaction potential, and potential settlements), and derive properties for soil-structure interaction studies. This document (Volume 5) contains the laboratory test results for the In-Tank Precipitation Facility (ITP) and H-Tank Farm (HTF) Geotechnical Report.

  10. Record of Decision Tank Farm Soil and INTEC Groundwater

    SciTech Connect

    L. S. Cahn

    2007-05-01

    This decision document presents the selected remedy for Operable Unit (OU) 3-14 tank farm soil and groundwater at the Idaho Nuclear Technology and Engineering Center (INTEC), which is located on the Idaho National Laboratory (INL) Site. The tank farm was initially evaluated in the OU 3-13 Record of Decision (ROD), and it was determined that additional information was needed to make a final decision. Additional information has been obtained on the nature and extent of contamination in the tank farm and on the impact of groundwater. The selected remedy was chosen in accordance with the Comprehensive Environmental Response, Liability and Compensation Act of 1980 (CERCLA) (42 USC 9601 et seq.), as amended by the Superfund Amendments and Reauthorization Act of 1986 (Public Law 99-499) and the National Oil and Hazardous Substances Pollution Contingency Plan (40 CFR 300). The selected remedy is intended to be the final action for tank far soil and groundwater at INTEC.

  11. PCB extraction from ORNL tank WC-14 using a unique solvent

    SciTech Connect

    Bloom, G.A.; Lucero, A.J.; Koran, L.J.; Turner, E.N.

    1995-09-01

    This report summarizes the development work of the Engineering Development Section of the Chemical Technology Division at Oak Ridge National Laboratory (ORNL) for an organic extraction method for removing polychlorinated biphenyls (PCBs) from tank WC-14. Tank WC-14 is part of the ORNL liquid low-level radioactive tank waste system and does not meet new secondary containment and leak detection regulations. These regulations require the tank to be taken out of service, and remediated before tank removal. To remediate the tank, the PCBs must be removed; the tank contents can then be transferred to the Melton Valley Storage Tanks before final disposal. The solvent being used for the PCB extraction experiments is triethylamine, an aliphatic amine that is soluble in water below 60{degrees}F but insoluble in water above 90{degrees}F. This property will allow the extraction to be carried out under fully miscible conditions within the tank; then, after tank conditions have been changed, the solvent will not be miscible with water and phase separation will occur. Phase separation between sludge, water, and solvent will allow solvent (loaded with PCBs) to be removed from the tank for disposal. After removing the PCBs from the sludge and removing the sludge from the tank, administrative control of the tank can be transferred to ORNL`s Environmental Restoration Program, where priorities will be set for tank removal. Experiments with WC-14 sludge show that greater than 90% extraction efficiencies can be achieved with one extraction stage and that PCB concentration in the sludge can be reduced to below 2 ppm in three extractions. It is anticipated that three extractions will be necessary to reduce the PCB concentration to below 2 ppm during field applications. The experiments conducted with tank WC-14 sludge transferred less than 0.03% of the original alpha contamination and less than 0.002% of the original beta contamination.

  12. Evidence for dawsonite in Hanford high-level nuclear waste tanks.

    PubMed

    Reynolds, Jacob G; Cooke, Gary A; Herting, Daniel L; Warrant, R Wade

    2012-03-30

    Gibbsite [Al(OH)(3)] and boehmite (AlOOH) have long been assumed to be the most prevalent aluminum-bearing minerals in Hanford high-level nuclear waste sludge. The present study shows that dawsonite [NaAl(OH)(2)CO(3)] is also a common aluminum-bearing phase in tanks containing high total inorganic carbon (TIC) concentrations and (relatively) low dissolved free hydroxide concentrations. Tank samples were probed for dawsonite by X-ray Diffraction (XRD), Scanning Electron Microscopy with Energy Dispersive Spectrometry (SEM-EDS) and Polarized Light Optical Microscopy. Dawsonite was conclusively identified in four of six tanks studied. In a fifth tank (AN-102), the dawsonite identification was less conclusive because it was only observed as a Na-Al bearing phase with SEM-EDS. Four of the five tank samples with dawsonite also had solid phase Na(2)CO(3) · H(2)O. The one tank without observable dawsonite (Tank C-103) had the lowest TIC content of any of the six tanks. The amount of TIC in Tank C-103 was insufficient to convert most of the aluminum to dawsonite (Al:TIC mol ratio of 20:1). The rest of the tank samples had much lower Al:TIC ratios (between 2:1 and 0.5:1) than Tank C-103. One tank (AZ-102) initially had dawsonite, but dawsonite was not observed in samples taken 15 months after NaOH was added to the tank surface. When NaOH was added to a laboratory sample of waste from Tank AZ-102, the ratio of aluminum to TIC in solution was consistent with the dissolution of dawsonite. The presence of dawsonite in these tanks is of significance because of the large amount of OH(-) consumed by dawsonite dissolution, an effect confirmed with AZ-102 samples.

  13. Storage tanks under earthquake loading

    SciTech Connect

    Rammerstorfer, F.G.; Scharf, K. ); Fisher, F.D. )

    1990-11-01

    This is a state-of-the-art review of various treatments of earthquake loaded liquid filled shells by the methods of earthquake engineering, fluid dynamics, structural and soil dynamics, as well as the theory of stability and computational mechanics. Different types of tanks and different possibilities of tank failure will be discussed. The authors will emphasize cylindrical above-ground liquid storage tanks with vertical axis. But many of the treatments are also valid for other tank configurations. For the calculation of the dynamically activated pressure due to an earthquake a fluid-structure-soil interaction problem must be solved. The review will describe the methods, proposed by different authors, to solve this interaction problem. To study the dynamic behavior of liquid storage tanks, one must distinguish between anchored and unanchored tanks. In the case of an anchored tank, the tank bottom edge is fixed to the foundation. If the tank is unanchored, partial lifting of the tank's bottom may occur, and a strongly nonlinear problem has to be solved. They will compare the various analytical and numerical models applicable to this problem, in combination with experimental data. An essential aim of this review is to give a summary of methods applicable as tools for an earthquake resistant design, which can be used by an engineer engaged in the construction of liquid storage tanks.

  14. ADMP Mixing of Tank 18F: History, Modeling, Testing, and Results

    SciTech Connect

    LEISHEAR, ROBERTA

    2004-03-29

    Residual radioactive waste was removed from Tank 18F in the F-Area Tank Farm at Savannah River Site (SRS), using the advanced design mixer pump (ADMP). Known as a slurry pump, the ADMP is a 55 foot long pump with an upper motor mounted to a steel super structure, which spans the top of the waste tank. The motor is connected by a long vertical drive shaft to a centrifugal pump, which is submerged in waste near the tank bottom. The pump mixes, or slurries, the waste within the tank so that it may be transferred out of the tank. Tank 18F is a 1.3 million gallon, 85 foot diameter underground waste storage tank, which has no internal components such as cooling coils or structural supports. The tank contained a residual 47,000 gallons of nuclear waste, consisting of a gelatinous radioactive waste known as sludge and particulate zeolite. The prediction of the ADMP success was based on nearly twenty five years of research and the application of that research to slurry pump technology. Many personnel at SRS and Pacific Northwest National Laboratories (PNNL) have significantly contributed to these efforts. This report summarizes that research which is pertinent to the ADMP performance in Tank 18F. In particular, a computational fluid dynamics (CFD) model was applied to predict the performance of the ADMP in Tank 18F.

  15. Regulatory issues associated with closure of the Hanford AX Tank Farm ancillary equipment

    SciTech Connect

    Becker, D.L.

    1998-09-02

    Liquid mixed, high-level radioactive waste has been stored in underground single-shell tanks at the US Department of Energy`s (DOE`s) Hanford Site. After retrieval of the waste from the single-shell tanks, the DOE will proceed with closure of the tank farm. The 241-AX Tank Farm includes four one-million gallon single-shell tanks in addition to sluice lines, transfer lines, ventilation headers, risers, pits, cribs, catch tanks, buildings, well and associated buried piping. This equipment is classified as ancillary equipment. This document addresses the requirements for regulatory close of the ancillary equipment in the Hanford Site 241-AX Tank Farm. The options identified for physical closure of the ancillary equipment include disposal in place, disposal in place after treatment, excavation and disposal on site in an empty single-shell tank, and excavation and disposal outside the AX Tank Farm. The document addresses the background of the Hanford Site and ancillary equipment in the AX Tank Farm, regulations for decontamination and decommissioning of radioactively contaminated equipment, requirements for the cleanup and disposal of radioactive wastes, cleanup and disposal requirements governing hazardous and mixed waste, and regulatory requirements and issues associated with each of the four physical closure options. This investigation was conducted by the Sandia National Laboratories, Albuquerque, New Mexico, during Fiscal Year 1998 for the Hanford Tanks Initiative Project.

  16. HANFORD DOUBLE SHELL TANK (DST) THERMAL & SEISMIC PROJECT SEISMIC ANALYSIS OF HANFORD DOUBLE SHELL TANKS

    SciTech Connect

    MACKEY, T.C.

    2006-03-17

    M&D Professional Services, Inc. (M&D) is under subcontract to Pacific Northwest National Laboratory (PNNL) to perform seismic analysis of the Hanford Site double-shell tanks (DSTs) in support of a project entitled ''Double-Shell Tank (DSV Integrity Project--DST Thermal and Seismic Analyses)''. The overall scope of the project is to complete an up-to-date comprehensive analysis of record of the DST system at Hanford in support of Tri-Party Agreement Milestone M-48-14, The work described herein was performed in support of the seismic analysis of the DSTs. The thermal and operating loads analysis of the DSTs is documented in Rinker et al. (2004). The work statement provided to M&D (PNNL 2003) required that the seismic analysis of the DSTs assess the impacts of potentially non-conservative assumptions in previous analyses and account for the additional soil mass due to the as-found soil density increase, the effects of material degradation, additional thermal profiles applied to the full structure including the soil-structure response with the footings, the non-rigid (low frequency) response of the tank roof, the asymmetric seismic-induced soil loading, the structural discontinuity between the concrete tank wall and the support footing and the sloshing of the tank waste. The seismic analysis considers the interaction of the tank with the surrounding soil and the effects of the primary tank contents. The DSTs and the surrounding soil are modeled as a system of finite elements. The depth and width of the soil incorporated into the analysis model are sufficient to obtain appropriately accurate analytical results. The analyses required to support the work statement differ from previous analysis of the DSTs in that the soil-structure interaction (SSI) model includes several (nonlinear) contact surfaces in the tank structure, and the contained waste must be modeled explicitly in order to capture the fluid-structure interaction behavior between the primary tank and contained

  17. 125. ARAI Contaminated waste storage tank (ARA729). Shows location of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    125. ARA-I Contaminated waste storage tank (ARA-729). Shows location of tank on the ARA-I site, section views, connecting pipeline, and other details. Norman Engineering Company 961-area/SF-301-3. Date: January 1959. Ineel index code no. 068-0301-00-613-102711. - Idaho National Engineering Laboratory, Army Reactors Experimental Area, Scoville, Butte County, ID

  18. IET. Tank building (TAN627). Plans, elevation, details. shows position of ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    IET. Tank building (TAN-627). Plans, elevation, details. shows position of tanks within building and concrete supports. Ralph M. Parsons 902-4-ANP-627-A&S 420. Date: Fabruary 1954. Approved by INEEL Classification Office for public release. INEEL index code no. 035-0627-00-693-106975 - Idaho National Engineering Laboratory, Test Area North, Scoville, Butte County, ID

  19. Sample Results From The Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples

    SciTech Connect

    Peters, T. B.; Fink, S. D.

    2012-12-20

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

  20. Sample Results from the Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples

    SciTech Connect

    Peters, T. B.; Fink, S. D.

    2012-12-11

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

  1. Determining Fuel Losses in Storage Tanks Based on Factual Saturation Pressures

    NASA Astrophysics Data System (ADS)

    Levitin, R. E.; Tryascin, R. A.

    2016-10-01

    At present, evaluation of fuel evaporative losses is based on a number of indirect parameters. Accuracy of such methods leaves much to be desired. The paper presents a method developed following the author's laboratory tests. An effective operation range of pressure vent valves in various tanks is provided, as well as low A92 gasoline losses for horizontal steel tanks at all operation temperatures.

  2. Tank Vapor Characterization Project: Annual status report for FY 1996

    SciTech Connect

    Silvers, K.L.; Fruchter, J.S.; Huckaby, J.L.; Almeida, T.L.; Evans, J.C. Jr.; Pool, K.H.; Simonen, C.A.; Thornton, B.M.

    1997-01-01

    In Fiscal Year 1996, staff at the Vapor Analytical Laboratory at Pacific Northwest National Laboratory performed work in support of characterizing the vapor composition of the headspaces of radioactive waste tanks at the Hanford Site. Work performed included support for technical issues and sampling methodologies, upgrades for analytical equipment, analytical method development, preparation of unexposed samples, analyses of tank headspaces samples, preparation of data reports, and operation of the tank vapor database. Progress made in FY 1996 included completion and issuance of 50 analytical data reports. A sampling system comparison study was initiated and completed during the fiscal year. The comparison study involved the vapor sampling system (VSS), a truck-based system, and the in situ vapor sampling system (ISVS), a cart-based system. Samples collected during the study were characterized for inorganic, permanent gases, total non-methane organic compounds and organic speciation by SUMMA{trademark} and TST methods. The study showed comparable sampling results between the systems resulting in the program switching from the VSS to the less expensive ISVS methodology in late May 1996. A temporal study was initiated in January 1996 in order to understand the influences seasonal temperatures changes have on the vapors in the headspace of Hanford waste tanks. A holding time study was initiated in the fourth quarter of FY 1996. Samples were collected from tank S-102 and rushed to the laboratory for time zero analysis. Additional samples will be analyzed at 1, 2, 4, 8, 16, and 32 weeks.

  3. TankSIM: A Cryogenic Tank Performance Prediction Program

    NASA Technical Reports Server (NTRS)

    Bolshinskiy, L. G.; Hedayat, A.; Hastings, L. J.; Moder, J. P.; Schnell, A. R.; Sutherlin, S. G.

    2015-01-01

    Accurate prediction of the thermodynamic state of the cryogenic propellants in launch vehicle tanks is necessary for mission planning and successful execution. Cryogenic propellant storage and transfer in space environments requires that tank pressure be controlled. The pressure rise rate is determined by the complex interaction of external heat leak, fluid temperature stratification, and interfacial heat and mass transfer. If the required storage duration of a space mission is longer than the period in which the tank pressure reaches its allowable maximum, an appropriate pressure control method must be applied. Therefore, predictions of the pressurization rate and performance of pressure control techniques in cryogenic tanks are required for development of cryogenic fluid long-duration storage technology and planning of future space exploration missions. This paper describes an analytical tool, Tank System Integrated Model (TankSIM), which can be used for modeling pressure control and predicting the behavior of cryogenic propellant for long-term storage for future space missions. It is written in the FORTRAN 90 language and can be compiled with any Visual FORTRAN compiler. A thermodynamic vent system (TVS) is used to achieve tank pressure control. Utilizing TankSIM, the following processes can be modeled: tank self-pressurization, boiloff, ullage venting, and mixing. Details of the TankSIM program and comparisons of its predictions with test data for liquid hydrogen and liquid methane will be presented in the final paper.

  4. Tank characterization data report: Tank 241-C-112

    SciTech Connect

    Simpson, B.C.; Borsheim, G.L.; Jensen, L.

    1993-04-01

    Tank 241-C-112 is a Hanford Site Ferrocyanide Watch List tank that was most recently sampled in March 1992. Analyses of materials obtained from tank 241-C-112 were conducted to support the resolution of the Ferrocyanide Unreviewed Safety Question (USQ) and to support Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-10-00. Analysis of core samples obtained from tank 241-C-112 strongly indicates that the fuel concentration in the tank waste will not support a propagating exothermic reaction. It is probable that tank 241-C-112 exceeds the 1,000 g-mol inventory criteria established for the Ferrocyanide USQ; however, extensive energetic analysis of the waste has determined a maximum exothermic value of -9 cal/g dry waste. This value is substantially below any levels of concern (-75 cal/g). In addition, an investigation of potential mechanisms to generate concentration levels of radionuclides high enough to be of concern was performed. No credible mechanism was postulated that could initiate the formation of such concentration levels in the tank. Tank 241-C-112 waste is a complex material made up primarily of water and inert salts. The insoluble solids are a mixture of phosphates, sulfates, and hydroxides in combination with aluminum, calcium, iron, nickel, and uranium. Disodium nickel ferrocyanide and sodium cesium nickel ferrocyanide probably exist in the tank; however, there appears to have been significant degradation of this material since the waste was initially settled in the tank.

  5. DEVELOPMENT OF ANSYS FINITE ELEMENT MODELS FOR SINGLE SHELL TANK (SST) & DOUBLE SHELL TANK (DST) TANKS

    SciTech Connect

    JULYK, L.J.; MACKEY, T.C.

    2003-06-19

    Summary report of ANSYS finite element models developed for dome load analysis of Hanford 100-series single-shell tanks and double-shell tanks. Document provides user interface for selecting proper tank model and changing of analysis parameters for tank specific analysis. Current dome load restrictions for the Hanford Site underground waste storage tanks are based on existing analyses of record (AOR) that evaluated the tanks for a specific set of design load conditions. However, greater flexibility is required in controlling dome loadings applied to the tanks due to day-to-day operations and waste retrieval activities. This requires the development of an analytical model with sufficient detail to evaluate various dome loading conditions not specifically addressed in the AOR.

  6. Tank 241-AP-105, cores 208, 209 and 210, analytical results for the final report

    SciTech Connect

    Nuzum, J.L.

    1997-10-24

    This document is the final laboratory report for Tank 241-AP-105. Push mode core segments were removed from Risers 24 and 28 between July 2, 1997, and July 14, 1997. Segments were received and extruded at 222-S Laboratory. Analyses were performed in accordance with Tank 241-AP-105 Push Mode Core Sampling and Analysis Plan (TSAP) (Hu, 1997) and Tank Safety Screening Data Quality Objective (DQO) (Dukelow, et al., 1995). None of the subsamples submitted for total alpha activity (AT), differential scanning calorimetry (DSC) analysis, or total organic carbon (TOC) analysis exceeded the notification limits as stated in TSAP and DQO. The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems Technical Basis Group, and are not considered in this report. Appearance and Sample Handling Two cores, each consisting of four segments, were expected from Tank 241-AP-105. Three cores were sampled, and complete cores were not obtained. TSAP states core samples should be transported to the laboratory within three calendar days from the time each segment is removed from the tank. This requirement was not met for all cores. Attachment 1 illustrates subsamples generated in the laboratory for analysis and identifies their sources. This reference also relates tank farm identification numbers to their corresponding 222-S Laboratory sample numbers.

  7. Tank 241-S-102, Core 232 analytical results for the final report

    SciTech Connect

    STEEN, F.H.

    1998-11-04

    This document is the analytical laboratory report for tank 241-S-102 push mode core segments collected between March 5, 1998 and April 2, 1998. The segments were subsampled and analyzed in accordance with the Tank 241-S-102 Retained Gas Sampler System Sampling and Analysis Plan (TSAP) (McCain, 1998), Letter of Instruction for Compatibility Analysis of Samples from Tank 241-S-102 (LOI) (Thompson, 1998) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO) (Mulkey and Miller, 1998). The analytical results are included in the data summary table (Table 1).

  8. AN ASSESSMENT OF THE SERVICE HISTORY AND CORROSION SUSCEPTIBILITY OF TYPE IV WASTE TANKS

    SciTech Connect

    Wiersma, B

    2008-09-18

    Type IV waste tanks were designed and built to store waste that does not require auxiliary cooling. Each Type IV tank is a single-shell tank constructed of a steel-lined pre-stressed concrete tank in the form of a vertical cylinder with a concrete domed roof. There are four such tanks in F-area, Tanks 17-20F, and four in H-Area, Tanks 21-24H. Leak sites were discovered in the liners for Tanks 19 and 20F in the 1980's. Although these leaks were visually observed, the investigation to determine the mechanism by which the leaks had occurred was not completed at that time. Therefore, a concern was raised that the same mechanism which caused the leak sites in the Tanks in F-area may also be operable in the H-Area tanks. Data from the construction of the tanks (i.e., certified mill test reports for the steel, no stress-relief), the service history (i.e., waste sample data, temperature data), laboratory tests on actual wastes and simulants (i.e., electrochemical testing), and the results of the visual inspections were reviewed. The following observations and conclusions were made: (1) Comparison of the compositional and microstructural features indicate that the A212 material utilized for construction of the H-Area tanks are far more resistant to SCC than the A285 materials used for construction of the F-Area tanks. (2) A review of the materials of construction, temperature history, service histories concluded that F-Area tanks likely failed by caustic stress corrosion cracking. (3) The environment in the F-Area tanks was more aggressive than that experienced by the H-Area tanks. (4) Based on a review of the service history, the H-Area tanks have not been exposed to an environment that would render the tanks susceptible to either nitrate stress corrosion cracking (i.e., the cause of failures in the Type I and II tanks) or caustic stress corrosion cracking. (5) Due to the very dilute and uninhibited solutions that have been stored in Tank 23H, vapor space corrosion has

  9. PROCESS WATER BUILDING, TRA605. SUMP TANK PUMP. COMPARE WITH ID33G247. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    PROCESS WATER BUILDING, TRA-605. SUMP TANK PUMP. COMPARE WITH ID-33-G-247. INL NEGATIVE NO. 4378. Unknown Photographer, 3/5/1952 - Idaho National Engineering Laboratory, Test Reactor Area, Materials & Engineering Test Reactors, Scoville, Butte County, ID

  10. Results of Retrieval Studies with Waste from Tank 241-C-104

    SciTech Connect

    O'ROURKE, J.F.

    2000-02-08

    Laboratory studies were performed on samples of waste from Tank 241-C-104. Physical property data was gathered to develop engineering plans for retrieval operations. Chemical composition data was collected to verify the ability to meet contract feed specifications.

  11. Tank 241-BY-111, cores 168 and 171 analytical results for the final report

    SciTech Connect

    Nuzum, J.L.

    1997-05-02

    This document is the final laboratory report for Tank 241-BY-111. Push mode core segments were removed from risers 15 and 12A between August 13, 1996, and September 3, 1996. Segments were received and extruded at 222-S Laboratory. Analyses were performed in accordance with Tank 241-BY-111 Rotary Mode Core Sampling and Analysis Plan (TSAP) (Kruger, 1996) and Safety Screening Data Quality Objective (DQO) (Dukelow, et al., 1995). None of the subsamples submitted for total alpha activity (AT) or differential scanning calorimetry (DSC) analyses exceeded the notification limits stated in DQO. Two cores of nine segments were expected from this tank. Sampling problems prevented the acquisition of complete cores. Attachment 1 illustrates subsamples generated in the laboratory for analysis and identifies their sources. This reference also relates tank farm identification numbers to their corresponding 222-S Laboratory Information Management System (LIMS) sample numbers.

  12. WRPS MEETING THE CHALLENGE OF TANK WASTE

    SciTech Connect

    BRITTON JC

    2012-02-21

    -and-a-half years to modernize the infrastructure in Hanford's tank farms. WRPS issued 850 subcontracts totaling more than $152 million with nearly 76 percent of that total awarded to small businesses. WRPS used the funding to upgrade tank farm infrastructure, develop technologies to retrieve and consolidate tank waste and extend the life of two critical operating facilities needed to feed waste to the WTP. The 222-S Laboratory analyzes waste to support waste retrievals and transfers. The laboratory was upgraded to support future WTP operations with a new computer system, new analytical equipment, a new office building and a new climate-controlled warehouse. The 242-A Evaporator was upgraded with a control-room simulator for operator training and several upgrades to aging equipment. The facility is used to remove liquid from the tank waste, creating additional storage space, necessary for continued waste retrievals and WTP operation. The One System Integrated Project Team is ajoint effort ofWRPS and Bechtel National to identify and resolve common issues associated with commissioning, feeding and operating the Waste Treatment Plant. Two new facilities are being designed to support WTP hot commlsslomng. The Interim Hanford Storage project is planned to store canisters of immobilized high-level radioactive waste glass produced by the vitrification plant. The facility will use open racks to store the 15-foot long, two-foot diameter canisters of waste, which require remote handling. The Secondary Liquid Waste Treatment Project is a major upgrade to the existing Effluent Treatment Facility at Hanford so it can treat about 10 million gallons of liquid radioactive and hazardous effluent a year from the vitrification plant. The One System approach brings the staff of both companies together to identify and resolve WTP safety issues. A questioning attitude is encouraged and an open forum is maintained for employees to raise issues. WRPS is completing its mission safely with record

  13. Tank characterization data report: Tank 241-C-112

    SciTech Connect

    Simpson, B.C.; Borsheim, G.L.; Jensen, L.

    1993-09-01

    Tank 241-C-112 is a Hanford Site Ferrocyanide Watch List tank that was most recently sampled in March 1992. Analyses of materials obtained from tank 241-C-112 were conducted to support the resolution of the Ferrocyanide Unreviewed Safety Question (USQ) and to support Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-10-00. Analysis of core samples obtained from tank 241-C-112 strongly indicates that the fuel concentration in the tank waste will not support a propagating exothermic reaction. Analysis of the process history of the tank as well as studies of simulants provided valuable information about the physical and chemical condition of the waste. This information, in combination with the analysis of the tank waste, sup ports the conclusion that an exothermic reaction in tank 241-C-112 is not plausible. Therefore, the contents of tank 241-C-112 present no imminent threat to the workers at the Hanford Site, the public, or the environment from its forrocyanide inventory. Because an exothermic reaction is not credible, the consequences of this accident scenario, as promulgated by the General Accounting Office, are not applicable.

  14. Solid Phase Characterization of Tank 241-C-105 Grab Samples

    SciTech Connect

    Ely, T. M.; LaMothe, M. E.; Lachut, J. S.

    2016-01-11

    The solid phase characterization (SPC) of three grab samples from single-shell Tank 241-C-105 (C-105) that were received at the laboratory the week of October 26, 2015, has been completed. The three samples were received and broken down in the 11A hot cells.

  15. 36. DETAILS AND SECTIONS OF SHIELDING TANK, FUEL ELEMENT SUPPORT ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    36. DETAILS AND SECTIONS OF SHIELDING TANK, FUEL ELEMENT SUPPORT FRAME AND SUPPORT PLATFORM, AND SAFETY MECHANISM ASSEMBLY (SPRING-LOADED HINGE). F.C. TORKELSON DRAWING NUMBER 842-ARVFS-701-S-1. INEL INDEX CODE NUMBER: 075 0701 60 851 151975. - Idaho National Engineering Laboratory, Advanced Reentry Vehicle Fusing System, Scoville, Butte County, ID

  16. 16. VIEW OF JUNCTION BETWEEN CABLE CHASE AND SHIELDING TANK. ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    16. VIEW OF JUNCTION BETWEEN CABLE CHASE AND SHIELDING TANK. SHOWS CABLES AND LINES IN THE TRENCH, POLE OF FRAME ASSEMBLY, AND EQUIPMENT IN CONCRETE BOX ADJACENT TO CABLE CHASE. INEL PHOTO NUMBER 65-6178, TAKEN NOVEMBER 10, 1965. - Idaho National Engineering Laboratory, Advanced Reentry Vehicle Fusing System, Scoville, Butte County, ID

  17. REACTOR BASE, SOUTHEAST CORNER. INTERIOR WILL CONTAIN REACTOR TANK, COOLING ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    REACTOR BASE, SOUTHEAST CORNER. INTERIOR WILL CONTAIN REACTOR TANK, COOLING WATER PIPES, COOLING AIR DUCTS, AND SHIELDING. INL NEGATIVE NO. 776. Unknown Photographer, 10/1950 - Idaho National Engineering Laboratory, Test Reactor Area, Materials & Engineering Test Reactors, Scoville, Butte County, ID

  18. 26. VIEW OF METAL SHED OVER SHIELDING TANK WITH CAMERA ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    26. VIEW OF METAL SHED OVER SHIELDING TANK WITH CAMERA FACING SOUTHWEST. SHOWS OPEN SIDE OF SHED ROOF, HERCULON SHEET, AND HAND-OPERATED CRANE. TAKEN IN 1983. INEL PHOTO NUMBER 83-476-2-9, TAKEN IN 1983. PHOTOGRAPHER NOT NAMED. - Idaho National Engineering Laboratory, Advanced Reentry Vehicle Fusing System, Scoville, Butte County, ID

  19. 3. EAST SIDE, ALSO SHOWING COVERED TANKS AND TEST STAND ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    3. EAST SIDE, ALSO SHOWING COVERED TANKS AND TEST STAND 1-5 AT RIGHT. - Edwards Air Force Base, Air Force Rocket Propulsion Laboratory, Test Stand 1-4, Test Area 1-115, northwest end of Saturn Boulevard, Boron, Kern County, CA

  20. 37. PLAN OF ACCESS CORRIDOR PIPING INCLUDES WASTE HOLD TANK ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    37. PLAN OF ACCESS CORRIDOR PIPING INCLUDES WASTE HOLD TANK CELL, OFFGAS CELL, ADSORBER CELL, AND OFFGAS FILTER CELL. INEEL DRAWING NUMBER 200-0633-00-287-106453. FLUOR NUMBER 5775-CPP-P-58. - Idaho National Engineering Laboratory, Old Waste Calcining Facility, Scoville, Butte County, ID

  1. 20. DECOMMISIONED HYDROGEN TANK IN FORMER LIQUID OXYGEN STORAGE AREA, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    20. DECOMMISIONED HYDROGEN TANK IN FORMER LIQUID OXYGEN STORAGE AREA, BETWEEN TEST STAND 1-A AND INSTRUMENTATION AND CONTROL BUILDING. Looking northwest. - Edwards Air Force Base, Air Force Rocket Propulsion Laboratory, Test Stand 1-A, Test Area 1-120, north end of Jupiter Boulevard, Boron, Kern County, CA

  2. 15. DETAIL SHOWING HYDROGEN (LEFT) AND OXYGEN (RIGHT) SPHERICAL TANKS ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    15. DETAIL SHOWING HYDROGEN (LEFT) AND OXYGEN (RIGHT) SPHERICAL TANKS ON RUN LINE DECK, THIRD LEVEL. DARK TONED PIPING IS THE FIRE EXTINGUISHING SYSTEM. Looking south southwest. - Edwards Air Force Base, Air Force Rocket Propulsion Laboratory, Test Stand 1-A, Test Area 1-120, north end of Jupiter Boulevard, Boron, Kern County, CA

  3. ONE MILLION GALLON WATER TANK, PUMP HEADER PIPE (AT LEFT), ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    ONE MILLION GALLON WATER TANK, PUMP HEADER PIPE (AT LEFT), HEADER BYPASS PIPE (AT RIGHT), AND PUMPHOUSE FOUNDATIONS. Looking northeast - Edwards Air Force Base, Air Force Rocket Propulsion Laboratory, Flame Deflector Water System, Test Area 1-120, north end of Jupiter Boulevard, Boron, Kern County, CA

  4. ANALYSIS OF THE TANK 5F FINAL CHARATERIZATION SAMPLES-2011

    SciTech Connect

    Oji, L.; Diprete, D.; Coleman, C.; Hay, M.

    2012-01-20

    The Savannah River National Laboratory (SRNL) was requested by SRR to provide sample preparation and analysis of the Tank 5F final characterization samples to determine the residual tank inventory prior to grouting. Two types of samples were collected and delivered to SRNL: floor samples across the tank and subsurface samples from mounds near risers 1 and 5 of Tank 5F. These samples were taken from Tank 5F between January and March 2011. These samples from individual locations in the tank (nine floor samples and six mound Tank 5F samples) were each homogenized and combined in a given proportion into 3 distinct composite samples to mimic the average composition in the entire tank. These Tank 5F composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 5F composite samples include bulk density and water leaching of the solids to account for water soluble species. With analyses for certain challenging radionuclides as the exception, all composite Tank 5F samples were analyzed and reported in triplicate. The target detection limits for isotopes analyzed were based on customer desired detection limits as specified in the technical task request documents. SRNL developed new methodologies to meet these target detection limits and provide data for the extensive suite of components. While many of the target detection limits were met for the species characterized for Tank 5F, as specified in the technical task request, some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The Technical Task Request allows that while the analyses of these isotopes is needed, meeting the detection limits for these isotopes is a lower priority than meeting detection limits for the other specified isotopes. The isotopes whose detection limits were not met in all cases included the

  5. ANALYSIS OF THE TANK 5F FINAL CHARACTERIZATION SAMPLES-2011

    SciTech Connect

    Oji, L.; Diprete, D.; Coleman, C.; Hay, M.

    2012-08-03

    The Savannah River National Laboratory (SRNL) was requested by SRR to provide sample preparation and analysis of the Tank 5F final characterization samples to determine the residual tank inventory prior to grouting. Two types of samples were collected and delivered to SRNL: floor samples across the tank and subsurface samples from mounds near risers 1 and 5 of Tank 5F. These samples were taken from Tank 5F between January and March 2011. These samples from individual locations in the tank (nine floor samples and six mound Tank 5F samples) were each homogenized and combined in a given proportion into 3 distinct composite samples to mimic the average composition in the entire tank. These Tank 5F composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 5F composite samples include bulk density and water leaching of the solids to account for water soluble species. With analyses for certain challenging radionuclides as the exception, all composite Tank 5F samples were analyzed and reported in triplicate. The target detection limits for isotopes analyzed were based on customer desired detection limits as specified in the technical task request documents. SRNL developed new methodologies to meet these target detection limits and provide data for the extensive suite of components. While many of the target detection limits were met for the species characterized for Tank 5F, as specified in the technical task request, some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The Technical Task Request allows that while the analyses of these isotopes is needed, meeting the detection limits for these isotopes is a lower priority than meeting detection limits for the other specified isotopes. The isotopes whose detection limits were not met in all cases included the

  6. Analysis Of The Tank 5F Final Characterization Samples-2011

    SciTech Connect

    Oji, L. N.; Diprete, D.; Coleman, C. J.; Hay, M. S.

    2012-09-27

    The Savannah River National Laboratory (SRNL) was requested by SRR to provide sample preparation and analysis of the Tank 5F final characterization samples to determine the residual tank inventory prior to grouting. Two types of samples were collected and delivered to SRNL: floor samples across the tank and subsurface samples from mounds near risers 1 and 5 of Tank 5F. These samples were taken from Tank 5F between January and March 2011. These samples from individual locations in the tank (nine floor samples and six mound Tank 5F samples) were each homogenized and combined in a given proportion into 3 distinct composite samples to mimic the average composition in the entire tank. These Tank 5F composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 5F composite samples include bulk density and water leaching of the solids to account for water soluble species. With analyses for certain challenging radionuclides as the exception, all composite Tank 5F samples were analyzed and reported in triplicate. The target detection limits for isotopes analyzed were based on customer desired detection limits as specified in the technical task request documents. SRNL developed new methodologies to meet these target detection limits and provide data for the extensive suite of components. While many of the target detection limits were met for the species characterized for Tank 5F, as specified in the technical task request, some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The Technical Task Request allows that while the analyses of these isotopes is needed, meeting the detection limits for these isotopes is a lower priority than meeting detection limits for the other specified isotopes. The isotopes whose detection limits were not met in all cases included the

  7. 46 CFR 153.266 - Tank linings.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 46 Shipping 5 2010-10-01 2010-10-01 false Tank linings. 153.266 Section 153.266 Shipping COAST... Tank linings. A tank lining must be: (a) At least as elastic as the tank material; and (b) Applied or attached to the tank as recommended by the lining manufacturer. Piping Systems and Cargo Handling Equipment...

  8. 27 CFR 19.183 - Scale tanks.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2011-04-01 2011-04-01 false Scale tanks. 19.183... Tank Requirements § 19.183 Scale tanks. (a) Except as otherwise provided in paragraph (b) of this..., the tank must be mounted on scales and the contents of the tank must be determined by weight....

  9. 27 CFR 19.183 - Scale tanks.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2014-04-01 2014-04-01 false Scale tanks. 19.183... Tank Requirements § 19.183 Scale tanks. (a) Except as otherwise provided in paragraph (b) of this..., the tank must be mounted on scales and the contents of the tank must be determined by weight....

  10. 27 CFR 19.183 - Scale tanks.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2013-04-01 2013-04-01 false Scale tanks. 19.183... Tank Requirements § 19.183 Scale tanks. (a) Except as otherwise provided in paragraph (b) of this..., the tank must be mounted on scales and the contents of the tank must be determined by weight....

  11. 27 CFR 19.183 - Scale tanks.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2012-04-01 2012-04-01 false Scale tanks. 19.183... Tank Requirements § 19.183 Scale tanks. (a) Except as otherwise provided in paragraph (b) of this..., the tank must be mounted on scales and the contents of the tank must be determined by weight....

  12. 49 CFR 238.423 - Fuel tanks.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Fuel tanks. 238.423 Section 238.423 Transportation....423 Fuel tanks. (a) External fuel tanks. Each type of external fuel tank must be approved by FRA's Associate Administrator for Safety upon a showing that the fuel tank provides a level of safety at...

  13. 49 CFR 238.423 - Fuel tanks.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 49 Transportation 4 2012-10-01 2012-10-01 false Fuel tanks. 238.423 Section 238.423 Transportation....423 Fuel tanks. (a) External fuel tanks. Each type of external fuel tank must be approved by FRA's Associate Administrator for Safety upon a showing that the fuel tank provides a level of safety at...

  14. 49 CFR 238.423 - Fuel tanks.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 49 Transportation 4 2013-10-01 2013-10-01 false Fuel tanks. 238.423 Section 238.423 Transportation....423 Fuel tanks. (a) External fuel tanks. Each type of external fuel tank must be approved by FRA's Associate Administrator for Safety upon a showing that the fuel tank provides a level of safety at...

  15. 49 CFR 238.423 - Fuel tanks.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 4 2011-10-01 2011-10-01 false Fuel tanks. 238.423 Section 238.423 Transportation....423 Fuel tanks. (a) External fuel tanks. Each type of external fuel tank must be approved by FRA's Associate Administrator for Safety upon a showing that the fuel tank provides a level of safety at...

  16. 49 CFR 238.423 - Fuel tanks.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 49 Transportation 4 2014-10-01 2014-10-01 false Fuel tanks. 238.423 Section 238.423 Transportation....423 Fuel tanks. (a) External fuel tanks. Each type of external fuel tank must be approved by FRA's Associate Administrator for Safety upon a showing that the fuel tank provides a level of safety at...

  17. 46 CFR 154.420 - Tank design.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... SELF-PROPELLED VESSELS CARRYING BULK LIQUEFIED GASES Design, Construction and Equipment Integral Tanks § 154.420 Tank design. (a) The structure of an integral tank must meet the deep tank scantling standards.... (b) The structure of an integral tank must be designed and shown by calculation to withstand...

  18. 14 CFR 23.1013 - Oil tanks.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Oil tanks. 23.1013 Section 23.1013... tanks. (a) Installation. Each oil tank must be installed to— (1) Meet the requirements of § 23.967 (a...) Expansion space. Oil tank expansion space must be provided so that— (1) Each oil tank used with...

  19. 27 CFR 25.35 - Tanks.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Tanks. 25.35 Section 25.35... TREASURY LIQUORS BEER Construction and Equipment Equipment § 25.35 Tanks. Each stationary tank, vat, cask... contents of tanks or containers in lieu of providing each tank or container with a measuring device....

  20. 49 CFR 230.116 - Oil tanks.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Oil tanks. 230.116 Section 230.116 Transportation... Locomotive Tanks § 230.116 Oil tanks. The oil tanks on oil burning steam locomotives shall be maintained free... adjacent to the fuel supply tank or in another safe location; (b) Closes automatically when tripped...

  1. 46 CFR 154.439 - Tank design.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 46 Shipping 5 2010-10-01 2010-10-01 false Tank design. 154.439 Section 154.439 Shipping COAST... Tank Type A § 154.439 Tank design. An independent tank type A must meet the deep tank standard of the...: (a) Withstand the internal pressure determined under § 154.407; (b) Withstand loads from...

  2. 46 CFR 154.439 - Tank design.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 46 Shipping 5 2011-10-01 2011-10-01 false Tank design. 154.439 Section 154.439 Shipping COAST... SELF-PROPELLED VESSELS CARRYING BULK LIQUEFIED GASES Design, Construction and Equipment Independent Tank Type A § 154.439 Tank design. An independent tank type A must meet the deep tank standard of...

  3. 46 CFR 154.439 - Tank design.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 46 Shipping 5 2014-10-01 2014-10-01 false Tank design. 154.439 Section 154.439 Shipping COAST... SELF-PROPELLED VESSELS CARRYING BULK LIQUEFIED GASES Design, Construction and Equipment Independent Tank Type A § 154.439 Tank design. An independent tank type A must meet the deep tank standard of...

  4. 46 CFR 154.439 - Tank design.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 46 Shipping 5 2012-10-01 2012-10-01 false Tank design. 154.439 Section 154.439 Shipping COAST... SELF-PROPELLED VESSELS CARRYING BULK LIQUEFIED GASES Design, Construction and Equipment Independent Tank Type A § 154.439 Tank design. An independent tank type A must meet the deep tank standard of...

  5. 46 CFR 154.439 - Tank design.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 46 Shipping 5 2013-10-01 2013-10-01 false Tank design. 154.439 Section 154.439 Shipping COAST... SELF-PROPELLED VESSELS CARRYING BULK LIQUEFIED GASES Design, Construction and Equipment Independent Tank Type A § 154.439 Tank design. An independent tank type A must meet the deep tank standard of...

  6. 46 CFR 154.420 - Tank design.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... SELF-PROPELLED VESSELS CARRYING BULK LIQUEFIED GASES Design, Construction and Equipment Integral Tanks § 154.420 Tank design. (a) The structure of an integral tank must meet the deep tank scantling standards.... (b) The structure of an integral tank must be designed and shown by calculation to withstand...

  7. 46 CFR 154.420 - Tank design.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... SELF-PROPELLED VESSELS CARRYING BULK LIQUEFIED GASES Design, Construction and Equipment Integral Tanks § 154.420 Tank design. (a) The structure of an integral tank must meet the deep tank scantling standards.... (b) The structure of an integral tank must be designed and shown by calculation to withstand...

  8. 46 CFR 154.420 - Tank design.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... SELF-PROPELLED VESSELS CARRYING BULK LIQUEFIED GASES Design, Construction and Equipment Integral Tanks § 154.420 Tank design. (a) The structure of an integral tank must meet the deep tank scantling standards.... (b) The structure of an integral tank must be designed and shown by calculation to withstand...

  9. 46 CFR 154.420 - Tank design.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... SELF-PROPELLED VESSELS CARRYING BULK LIQUEFIED GASES Design, Construction and Equipment Integral Tanks § 154.420 Tank design. (a) The structure of an integral tank must meet the deep tank scantling standards.... (b) The structure of an integral tank must be designed and shown by calculation to withstand...

  10. Evaluation of the generation and release of flammable gases in tank 241-SY-101

    SciTech Connect

    Babad, H.; Johnson, G.D.; Lechelt, J.A.; Reynolds, D.A. ); Pederson, L.R.; Strachan, D.M. ); Meisel, D.; Jonah, C. ); Ashby, E.C. )

    1991-11-01

    Tank 241-SY-101 is a double shell, high-level waste tank located in the 200 West Area of the Hanford Site. This tank contains about 1 million gallons of waste that was concentrated at the 242-S Evaporator. Shortly after the waste was put in the tank, the waste began to expand because the generation of gases. In 1990 this tank was declared to have an unreviewed safety question because of the periodic release of hydrogen and nitrous oxide. A safety program was established to conduct a characterization of the waste and vented gases and to determine an effective means to prevent the accumulation of flammable gases in the tank dome space and ventilation system. Results of the expanded characterization conducted in fiscal year 1991 are presented. The use of gas chromatographs, mass spectrometers, and hydrogen-specific monitors provided a greater understanding of the vented gases. Additional instrumentation placed in the tank also helped to provide more detailed information on tank temperatures, gas pressure, and gas flow rates. An extensive laboratory study involving the Westinghouse Hanford Company, Pacific Northwest Laboratory, Argonne National Laboratory, and the Georgia Institute of Technology was initiated for the purpose of determining the mechanisms responsible for the generation of various gases. These studies evaluate both radiolytic and thermochemical processes. Results of the first series of experiments are described.

  11. Tank 241-SY-101 push mode core sampling and analysis plan

    SciTech Connect

    CONNER, J.M.

    1998-10-09

    This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for push mode core samples from tank 241-SY-101 (SY-101). It is written in accordance with Data Quality Objective to Support Resolution of the Flammable Gas Safety Issue (Bauer 1998), Low Activity Waste Feed Data Quality Objectives (Wiemers and Miller 1997 and DOE 1998), Data Quality Objectives for TWRS Privatization Phase I: Confirm Tank T is an Appropriate Feed Source for Low-Activity Waste Feed Batch X (Certa 1998), and the Tank Safety Screening Data Quality Objective (Dukelow et al. 1995). The Tank Characterization Technical Sampling Basis document (Brown et al. 1998) indicates that these issues apply to tank SY-101 for this sampling event. Brown et al. also identifies high-level waste, regulatory, pretreatment and disposal issues as applicable issues for this tank. However, these issues will not be addressed via this sampling event.

  12. Waste Tank Safety Program. Annual status report for FY 1993, Task 3: Organic chemistry

    SciTech Connect

    Lucke, R.B.; Clauss, T.T.W.; Hoheimer, R.; Goheen, S.C.

    1994-02-01

    This task supports the tank-vapor project, mainly by providing organic analytical support and by analyzing Tank 241-C-103 (Tank C-103) vapor-space samples, collected via SUMMA{trademark} canisters, by gas chromatography (GC) and GC/mass spectrometry (MS). In the absence of receiving tank-vapor samples, we have focused our efforts toward validating the normal paraffin hydrocarbon (NPH) sampling and analysis methods and preparing the SUMMA{trademark} laboratory. All required milestones were met, including a report on the update of phase I sampling and analysis on August 15, 1993. This update described the work involved in preparing to analyze phase I samples (Appendix A). This report describes the analytical support provided by Pacific Northwest Laboratory (PNL){sup (a)} to the Hanford Tank Safety Vapor Program.

  13. Tank 241-T-204, core 188 analytical results for the final report

    SciTech Connect

    Nuzum, J.L.

    1997-07-24

    TANK 241-T-204, CORE 188, ANALYTICAL RESULTS FOR THE FINAL REPORT. This document is the final laboratory report for Tank 241 -T-204. Push mode core segments were removed from Riser 3 between March 27, 1997, and April 11, 1997. Segments were received and extruded at 222-8 Laboratory. Analyses were performed in accordance with Tank 241-T-204 Push Mode Core Sampling and analysis Plan (TRAP) (Winkleman, 1997), Letter of instruction for Core Sample Analysis of Tanks 241-T-201, 241- T-202, 241-T-203, and 241-T-204 (LAY) (Bell, 1997), and Safety Screening Data Qual@ Objective (DO) ODukelow, et al., 1995). None of the subsamples submitted for total alpha activity (AT) or differential scanning calorimetry (DC) analyses exceeded the notification limits stated in DO. The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems Technical Basis Group and are not considered in this report.

  14. Review of sensors for the in situ chemical characterization of the Hanford underground storage tanks

    SciTech Connect

    Kyle, K.R.; Mayes, E.L.

    1994-07-29

    Lawrence Livermore National Laboratory (LLNL), in the Technical Task Plan (TTP) SF-2112-03 subtask 2, is responsible for the conceptual design of a Raman probe for inclusion in the in-tank cone penetrometer. As part of this task, LLNL is assigned the further responsibility of generating a report describing a review of sensor technologies other than Raman that can be incorporated in the in-tank cone penetrometer for the chemical analysis of the tank environment. These sensors would complement the capabilities of the Raman probe, and would give information on gaseous, liquid, and solid state species that are insensitive to Raman interrogation. This work is part of a joint effort involving several DOE laboratories for the design and development of in-tank cone penetrometer deployable systems for direct UST waste characterization at Westinghouse Hanford Company (WHC) under the auspices of the U.S. Department of Energy (DOE) Underground Storage Tank Integrated Demonstration (UST-ID).

  15. Science Road Map for Phase 2 of the Tank-Farm Vadose Zone Program

    SciTech Connect

    Zachara, John M.; Freshley, Mark D.; Mann, Frederick M.

    2008-08-18

    Phase 1 of the Tank-Farm Vadose Zone Program (TFVZP) developed information on the nature and extent of vadose zone contamination in the tank farms through field studies, laboratory analyses and experiments, and historical data searches; assembled data and performed tank-farm risk analysis; and initiated interim corrective actions to lessen the impacts of tank leak contaminants. Pacific Northwest National Laboratory scientists and external collaborators at universities and U.S. Department of Energy user facilities sampled and analyzed contaminant plumes. These types of activities will continue during Phase 2 of the TFVZP to refine and expand scientific understanding of the subsurface beneath tank farms, especially of water movement, residual waste leaching, and contaminant transport.

  16. Underground tank vitrification: A pilot-scale in situ vitrification test of a tank containing a simulated mixed waste sludge

    SciTech Connect

    Thompson, L.E.; Powell, T.D.; Tixier, J.S.; Miller, M.C.; Owczarski, P.C.

    1993-09-01

    This report documents research on sludge vitrification. The first pilot scale in-situ vitrification test of a simulated underground tank was successfully completed by researchers at Pacific Northwest Laboratory. The vitrification process effectively immobilized the vast majority of radionuclides simulants and toxic metals were retained in the melt and uniformly distributed throughout the monolith.

  17. Light Duty Utility Arm deployment in Tank WM-188

    SciTech Connect

    Patterson, M.W.

    1999-12-01

    The Light Duty Utility Arm (LDUA) was successfully deployed in Tank WM-188 during February and March of 1999 at the Idaho Nuclear Technology and Engineering Center (INTEC) tank farm at the Idaho National Engineering and Environmental Laboratory. Some equipment problems were identified, but most were indicative of any first time activity. Deployment during cold weather imposed additional equipment risks, but in general, equipment response to the winter conditions was better than expected. Three end effectors were demonstrated during the deployment. All performed as expected, although the limited resolution of the Alternating Current Field Measurement end effector cannot absolutely confirm tank integrity, which is necessary for future tank inspections. Four heel samples were taken with the sampler end effector and a broad spectrum of analyses were performed. A detailed inspection of the tank interior was performed with the High Resolution Stereo Video System end effector. The sample information is proving invaluable to the development of new treatment flowsheets and waste forms. It is expected that the LDUA will be deployed for tank inspections through the next several years to support other Notice of Non-Compliance (NON) Consent Order requirements and several other ongoing initiatives.

  18. Mechanistic analysis of double-shell tank gas release

    SciTech Connect

    Allemann, R.T.; Antoniak, Z.I.; Friley, J.R.; Haines, C.E.; Liljegren, L.M.; Somasundaram, S.

    1991-12-01

    Pacific Northwest Laboratory (PNL) is studying possible mechanisms and fluid dynamics contributing to the periodic release of gases from the double-shell waste storage tanks at Hanford. This study is being conducted for Westinghouse Hanford Company (WHC), a contractor for the US Department of Energy (DOE). This interim report discusses the work done through November 1990. Safe management of the wastes at Hanford depends on an understanding of the chemical and physical mechanisms that take place in the waste tanks. An example of the need to understand these mechanisms is tank 101-SY. The waste in this tank is generating and periodically releasing potentially flammable gases into the tank vent system according to observations of the tank. How these gases are generated and become trapped, the causes of periodic release, and the mechanism of the release are not known in detail. In order to develop a safe mitigation strategy, possible physical mechanisms for the periodic release of flammable gases need to be understood.

  19. Tank Focus Area Pretreatment Program. FY 1995 Program Management Plan

    SciTech Connect

    Morrison, M.I.; McGinnis, C.P.; Wilkenson, W.T.; Hunt, R.D.

    1995-02-01

    This program management plan (PMP) describes the FY 1995 project plans for the Pretreatment Program of the Tank Focus Area. The Tank Focus Area is one of five areas of environmental concerns originally identified by the Deputy Assistant Secretary for Technology Development (EM-50). Projects in the Tank Focus Area relate to the remediation of liquid waste stored in underground storage tanks at various US Department of Energy sites. The Pretreatment Program is an organizational unit performing work within the Tank Focus Area. The function of the Pretreatment Program is to develop, test, evaluate, and demonstrate new technologies, with emphasis on separations. The 11 Pretreatment Program projects for FY 1995 are (1) Cesium Extraction Testing, (2) Comprehensive Supernate Treatment, (3) Hot Cell Studies, (4) Cesium Removal Demonstration, (5) Out-of-Tank Evaporator Demonstration, (6) Crossflow Filtration, (7) Technical Interchange with CEA, (8) TRUEX Applications, (9) NAC/NAG Process Studies (conducted at Oak Ridge National Laboratory), (10) NAC/NAG Process and Waste Form Studies (conducted at Florida International University), and (11) Program Management. Section 2 of this PMP contains a separate subsection for each FY 1995 project. A brief description of the project, a schedule of major milestones, and a breakdown of costs are provided for each project. The PMP also contains sections that describe the project controls that are in place. Quality assurance, document control, the project management system, and the management organization are described in these sections.

  20. ORNL measurements at Hanford Waste Tank TX-118

    SciTech Connect

    Koehler, P.E.; Mihalczo, J.T.

    1995-02-01

    A program of measurements and calculations to develop a method of measuring the fissionable material content of the large waste storage tanks at the Hanford, Washington, site is described in this report. These tanks contain radioactive waste from the processing of irradiated fuel elements from the plutonium-producing nuclear reactors at the Hanford site. Time correlation and noise analysis techniques, similar to those developed for and used in the Nuclear Weapons Identification System at the Y-12 Plant in Oak Ridge, Tennessee, will be used at the Hanford site. Both ``passive`` techniques to detect the neutrons emitted spontaneously from the waste in the tank and ``active`` techniques using AmBe and {sup 252}Cf neutron sources to induce fissions will be used. This work is divided into three major tasks: (1) development of high-sensitivity neutron detectors that can selectively count only neutrons in the high {gamma} radiation fields in the tanks, (2) Monte Carlo neutron transport calculations using both the KENO and MCNP codes to plan and analyze the measurements, and (3) the measurement of time-correlated neutrons by time and frequency analysis to distinguish spontaneous fission from sources inside the tanks. This report describes the development of the detector and its testing in radiation fields at the Radiation Calibration Facility at Oak Ridge National Laboratory and in tank TX-118 at the 200 W area at Westinghouse Hanford Company.

  1. The modified swirl sedimentation tanks for water purification.

    PubMed

    Ochowiak, Marek; Matuszak, Magdalena; Włodarczak, Sylwia; Ancukiewicz, Małgorzata; Krupińska, Andżelika

    2017-03-15

    This paper discusses design, evaluation, and application for the use of swirl/vortex technologies as liquid purification system. A study was performed using modified swirl sedimentation tanks. The vortex separators (OW, OWK, OWR and OWKR) have been studied under laboratory conditions at liquid flow rate from 2.8⋅10(-5) to 5.1⋅10(-4) [m(3)/s]. The pressure drop and the efficiency of purification of liquid stream were analyzed. The suspended particles of different diameters were successfully removed from liquid with the application of swirl chambers of proposed constructions. It was found that damming of liquid in the tank increases alongside liquid stream at the inlet and depends on the tank construction. The efficiency of the sedimentation tanks increases alongside the diameters of solid particles and decrease in the liquid flow rate. The best construction proved to be the OWR sedimentation tank due to smallest liquid damming, even at high flow rates, and the highest efficiency of the purification liquid stream for solid particles of the smallest diameter. The proposed solution is an alternative to the classical constructions of sedimentation tanks.

  2. Probabilistic safety assessment for Hanford high-level waste tank 241-SY-101

    SciTech Connect

    MacFarlane, D.R.; Bott, T.F.; Brown, L.F.; Stack, D.W.; Kindinger, J.; Deremer, R.K.; Medhekar, S.R.; Mikschl, T.J.

    1994-05-01

    Los Alamos National Laboratory (Los Alamos) is performing a comprehensive probabilistic safety assessment (PSA), which will include consideration of external events for the 18 tank farms at the Hanford Site. This effort is sponsored by the Department of Energy (DOE/EM, EM-36). Even though the methodology described herein will be applied to the entire tank farm, this report focuses only on the risk from the weapons-production wastes stored in tank number 241-SY-101, commonly known as Tank 101-SY, as configured in December 1992. This tank, which periodically releases ({open_quotes}burps{close_quotes}) a gaseous mixture of hydrogen, nitrous oxide, ammonia, and nitrogen, was analyzed first because of public safety concerns associated with the potential for release of radioactive tank contents should this gas mixture be ignited during one of the burps. In an effort to mitigate the burping phenomenon, an experiment is being conducted in which a large pump has been inserted into the tank to determine if pump-induced circulation of the tank contents will promote a slow, controlled release of the gases. At the Hanford Site there are 177 underground tanks in 18 separate tank farms containing accumulated liquid/sludge/salt cake radioactive wastes from 50 yr of weapons materials production activities. The total waste volume is about 60 million gal., which contains approximately 120 million Ci of radioactivity.

  3. Engineering assessment and certification of integrity of the 325-I1U1 tank system

    SciTech Connect

    Schwartz, W W; Graser, D A

    1991-12-01

    This Engineering Assessment and Certification of Integrity of retention tank 325-I1U1 of Lawrence Livermore Laboratory has been prepared in response to 40 CFR 265.191 for an existing tank system that stores hazardous waste and does not have secondary containment. This technical assessment has been reviewed by an independent, qualified, California-registered professional engineer, who has certified the tank system to be adequately designed and compatible with the stored waste so that it will not collapse, rupture, or fail. Certification of the 325-I1U1 tank system is qualified by the fact that 40 CFR 265-193 requires that a system be upgraded to include secondary containment when it reaches 15 years of age or within two years after January 12, 1987, whichever comes later. Tank 325-I1U1 was built in 1968 and required upgrading to secondary containment by January 12, 1989. This Engineering Assessment has been prepared as Best Management practice since this tank system was in service after January 12, 1989, but is not in use at this time. This document will be kept on file at the facility. Certification and documentation of the onground retention tank 325-I1O1, which is part of the 325-I1 retention tank system, is not included in this assessment. A discussion of tank 325-I1O1, however, is included in this report to provide a complete description of the 325-I1 retention tank system.

  4. 33 CFR 157.208 - Dedicated Clean Ballast Tanks Operations Manual for foreign tank vessels: Submission.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Dedicated Clean Ballast Tanks... MARINE ENVIRONMENT RELATING TO TANK VESSELS CARRYING OIL IN BULK Dedicated Clean Ballast Tanks on Tank Vessels General § 157.208 Dedicated Clean Ballast Tanks Operations Manual for foreign tank...

  5. 46 CFR 153.250 - Double-bottom and deep tanks as cargo tanks.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 46 Shipping 5 2011-10-01 2011-10-01 false Double-bottom and deep tanks as cargo tanks. 153.250... Equipment Cargo Tanks § 153.250 Double-bottom and deep tanks as cargo tanks. Except in those cases in which Commandant (CG-522) specifically approves another arrangement, such as a double-bottom or deep tank as...

  6. 46 CFR 153.250 - Double-bottom and deep tanks as cargo tanks.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 46 Shipping 5 2012-10-01 2012-10-01 false Double-bottom and deep tanks as cargo tanks. 153.250... Equipment Cargo Tanks § 153.250 Double-bottom and deep tanks as cargo tanks. Except in those cases in which Commandant (CG-ENG) specifically approves another arrangement, such as a double-bottom or deep tank as...

  7. 46 CFR 153.250 - Double-bottom and deep tanks as cargo tanks.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 46 Shipping 5 2014-10-01 2014-10-01 false Double-bottom and deep tanks as cargo tanks. 153.250... Equipment Cargo Tanks § 153.250 Double-bottom and deep tanks as cargo tanks. Except in those cases in which Commandant (CG-ENG) specifically approves another arrangement, such as a double-bottom or deep tank as...

  8. 46 CFR 153.250 - Double-bottom and deep tanks as cargo tanks.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 46 Shipping 5 2013-10-01 2013-10-01 false Double-bottom and deep tanks as cargo tanks. 153.250... Equipment Cargo Tanks § 153.250 Double-bottom and deep tanks as cargo tanks. Except in those cases in which Commandant (CG-ENG) specifically approves another arrangement, such as a double-bottom or deep tank as...

  9. 46 CFR 153.250 - Double-bottom and deep tanks as cargo tanks.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 46 Shipping 5 2010-10-01 2010-10-01 false Double-bottom and deep tanks as cargo tanks. 153.250... Equipment Cargo Tanks § 153.250 Double-bottom and deep tanks as cargo tanks. Except in those cases in which Commandant (CG-522) specifically approves another arrangement, such as a double-bottom or deep tank as...

  10. 33 CFR 157.208 - Dedicated Clean Ballast Tanks Operations Manual for foreign tank vessels: Submission.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 33 Navigation and Navigable Waters 2 2012-07-01 2012-07-01 false Dedicated Clean Ballast Tanks... MARINE ENVIRONMENT RELATING TO TANK VESSELS CARRYING OIL IN BULK Dedicated Clean Ballast Tanks on Tank Vessels General § 157.208 Dedicated Clean Ballast Tanks Operations Manual for foreign tank...

  11. 33 CFR 157.208 - Dedicated Clean Ballast Tanks Operations Manual for foreign tank vessels: Submission.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 33 Navigation and Navigable Waters 2 2014-07-01 2014-07-01 false Dedicated Clean Ballast Tanks... MARINE ENVIRONMENT RELATING TO TANK VESSELS CARRYING OIL IN BULK Dedicated Clean Ballast Tanks on Tank Vessels General § 157.208 Dedicated Clean Ballast Tanks Operations Manual for foreign tank...

  12. 33 CFR 157.208 - Dedicated Clean Ballast Tanks Operations Manual for foreign tank vessels: Submission.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 33 Navigation and Navigable Waters 2 2011-07-01 2011-07-01 false Dedicated Clean Ballast Tanks... MARINE ENVIRONMENT RELATING TO TANK VESSELS CARRYING OIL IN BULK Dedicated Clean Ballast Tanks on Tank Vessels General § 157.208 Dedicated Clean Ballast Tanks Operations Manual for foreign tank...

  13. 33 CFR 157.208 - Dedicated Clean Ballast Tanks Operations Manual for foreign tank vessels: Submission.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 33 Navigation and Navigable Waters 2 2013-07-01 2013-07-01 false Dedicated Clean Ballast Tanks... MARINE ENVIRONMENT RELATING TO TANK VESSELS CARRYING OIL IN BULK Dedicated Clean Ballast Tanks on Tank Vessels General § 157.208 Dedicated Clean Ballast Tanks Operations Manual for foreign tank...

  14. 49 CFR 179.102 - Special commodity requirements for pressure tank car tanks.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... car tanks. 179.102 Section 179.102 Transportation Other Regulations Relating to Transportation... REGULATIONS SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.102 Special commodity requirements for pressure tank car tanks. (a) In addition...

  15. 49 CFR 179.103 - Special requirements for class 114A * * * tank car tanks.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false Special requirements for class 114A * * * tank car... SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.103 Special requirements for class 114A * * * tank car tanks. (a) In addition to the...

  16. 49 CFR 179.103 - Special requirements for class 114A * * * tank car tanks.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 3 2011-10-01 2011-10-01 false Special requirements for class 114A * * * tank car...) SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.103 Special requirements for class 114A * * * tank car tanks. (a) In addition to the...

  17. 27 CFR 24.229 - Tank car and tank truck requirements.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2014-04-01 2014-04-01 false Tank car and tank truck... BUREAU, DEPARTMENT OF THE TREASURY ALCOHOL WINE Spirits § 24.229 Tank car and tank truck requirements. Railroad tank cars and tank trucks used to transport spirits for use in wine production will be...

  18. 49 CFR 179.102 - Special commodity requirements for pressure tank car tanks.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... car tanks. 179.102 Section 179.102 Transportation Other Regulations Relating to Transportation...) SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.102 Special commodity requirements for pressure tank car tanks. (a) In addition to §§ 179.100...

  19. 49 CFR 179.100 - General specifications applicable to pressure tank car tanks.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... car tanks. 179.100 Section 179.100 Transportation Other Regulations Relating to Transportation...) SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.100 General specifications applicable to pressure tank car tanks....

  20. 49 CFR 179.103 - Special requirements for class 114A * * * tank car tanks.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 49 Transportation 3 2012-10-01 2012-10-01 false Special requirements for class 114A * * * tank car...) SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.103 Special requirements for class 114A * * * tank car tanks. (a) In addition to the...

  1. 49 CFR 179.100 - General specifications applicable to pressure tank car tanks.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... car tanks. 179.100 Section 179.100 Transportation Other Regulations Relating to Transportation... REGULATIONS SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.100 General specifications applicable to pressure tank car tanks....

  2. 49 CFR 179.102 - Special commodity requirements for pressure tank car tanks.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... car tanks. 179.102 Section 179.102 Transportation Other Regulations Relating to Transportation...) SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.102 Special commodity requirements for pressure tank car tanks. (a) In addition to §§ 179.100...

  3. 49 CFR 179.101 - Individual specification requirements applicable to pressure tank car tanks.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... to pressure tank car tanks. 179.101 Section 179.101 Transportation Other Regulations Relating to... (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.101 Individual specification requirements applicable to pressure tank...

  4. 27 CFR 24.229 - Tank car and tank truck requirements.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2012-04-01 2012-04-01 false Tank car and tank truck... BUREAU, DEPARTMENT OF THE TREASURY LIQUORS WINE Spirits § 24.229 Tank car and tank truck requirements. Railroad tank cars and tank trucks used to transport spirits for use in wine production will be...

  5. 27 CFR 24.229 - Tank car and tank truck requirements.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2013-04-01 2013-04-01 false Tank car and tank truck... BUREAU, DEPARTMENT OF THE TREASURY ALCOHOL WINE Spirits § 24.229 Tank car and tank truck requirements. Railroad tank cars and tank trucks used to transport spirits for use in wine production will be...

  6. 49 CFR 179.100 - General specifications applicable to pressure tank car tanks.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... car tanks. 179.100 Section 179.100 Transportation Other Regulations Relating to Transportation...) SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.100 General specifications applicable to pressure tank car tanks....

  7. 49 CFR 179.101 - Individual specification requirements applicable to pressure tank car tanks.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... to pressure tank car tanks. 179.101 Section 179.101 Transportation Other Regulations Relating to... (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.101 Individual specification requirements applicable to pressure tank...

  8. 49 CFR 179.100 - General specifications applicable to pressure tank car tanks.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... car tanks. 179.100 Section 179.100 Transportation Other Regulations Relating to Transportation...) SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.100 General specifications applicable to pressure tank car tanks....

  9. 49 CFR 179.101 - Individual specification requirements applicable to pressure tank car tanks.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... to pressure tank car tanks. 179.101 Section 179.101 Transportation Other Regulations Relating to... (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.101 Individual specification requirements applicable to pressure tank...

  10. 27 CFR 27.174 - Tank cars and tank trucks to be sealed.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2011-04-01 2011-04-01 false Tank cars and tank trucks... Tank cars and tank trucks to be sealed. Where a shipment of distilled spirits from customs custody to the distilled spirits plant is made in a tank car or tank truck, all openings affording access to...

  11. 27 CFR 27.174 - Tank cars and tank trucks to be sealed.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2014-04-01 2014-04-01 false Tank cars and tank trucks... Tank cars and tank trucks to be sealed. Where a shipment of distilled spirits from customs custody to the distilled spirits plant is made in a tank car or tank truck, all openings affording access to...

  12. 49 CFR 179.101 - Individual specification requirements applicable to pressure tank car tanks.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... to pressure tank car tanks. 179.101 Section 179.101 Transportation Other Regulations Relating to... (CONTINUED) SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.101 Individual specification requirements applicable to pressure tank...

  13. 27 CFR 24.229 - Tank car and tank truck requirements.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Tank car and tank truck... BUREAU, DEPARTMENT OF THE TREASURY LIQUORS WINE Spirits § 24.229 Tank car and tank truck requirements. Railroad tank cars and tank trucks used to transport spirits for use in wine production will be...

  14. 49 CFR 179.100 - General specifications applicable to pressure tank car tanks.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... car tanks. 179.100 Section 179.100 Transportation Other Regulations Relating to Transportation...) SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.100 General specifications applicable to pressure tank car tanks....

  15. 49 CFR 179.102 - Special commodity requirements for pressure tank car tanks.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... car tanks. 179.102 Section 179.102 Transportation Other Regulations Relating to Transportation...) SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.102 Special commodity requirements for pressure tank car tanks. (a) In addition to §§ 179.100...

  16. 27 CFR 27.174 - Tank cars and tank trucks to be sealed.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2012-04-01 2012-04-01 false Tank cars and tank trucks... Tank cars and tank trucks to be sealed. Where a shipment of distilled spirits from customs custody to the distilled spirits plant is made in a tank car or tank truck, all openings affording access to...

  17. 27 CFR 24.229 - Tank car and tank truck requirements.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2011-04-01 2011-04-01 false Tank car and tank truck... BUREAU, DEPARTMENT OF THE TREASURY LIQUORS WINE Spirits § 24.229 Tank car and tank truck requirements. Railroad tank cars and tank trucks used to transport spirits for use in wine production will be...

  18. 49 CFR 179.103 - Special requirements for class 114A * * * tank car tanks.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 49 Transportation 3 2013-10-01 2013-10-01 false Special requirements for class 114A * * * tank car...) SPECIFICATIONS FOR TANK CARS Specifications for Pressure Tank Car Tanks (Classes DOT-105, 109, 112, 114 and 120) § 179.103 Special requirements for class 114A * * * tank car tanks. (a) In addition to the...

  19. Chemical and physical processes in Tank 241-SY-101: A preliminary report

    SciTech Connect

    Not Available

    1991-02-01

    Since 1942, chemical and radioactive waste have been stored in underground tanks at the Hanford Site. In March 1981 one of the double shell tanks, 241-SY-101 (called 101-SY), began venting large quantities of gas, primarily hydrogen and nitrous oxide. Because of the potential for explosion Westinghouse Hanford Company and the US Department of Energy realized the need for knowledge about the processes occurring in this tank that lead to generation of the gases. In June 1990, the Pacific Northwest Laboratory began assembling a Tank Waste Science Panel to develop a better understanding of the processes occurring the Tank 101-SY. This knowledge is necessary to provide a technically defensible basis for the safety analyses, which will allow the tank contents to be sampled, as well as for the future remediation of the tank and its contents. The Panel concluded that the data available on Tank 101-SY are insufficient to allow the critical chemical and physical processes giving rise to gas formation and release to be unambiguously identified. To provide the needed information the Panel recommends that Tank 101-SY by physically and chemically characterized as fully as possible and as expeditiously as safety considerations allow, and laboratory studies and modeling efforts be undertaken the chemical and physical processes involved in gas generation and release. Finally, the Panel recommends that no remediation steps be taken until there is a better understanding of the chemical and physical phenomena occurring in Tank 101-SY. Premature remediation steps may only serve to compound the problem. Furthermore, such steps may change the chemical and physical characteristics of the tank and prevent a true understanding of the phenomena involved. As a consequence, similar problems in other tanks on the site may not be adequately addressed. 17 refs., 3 figs., 1 tab.

  20. Turbulent Kinetic Energy and Temperature Variance Dissipation in Laboratory Generated Rayleigh-Benard Turbulence Designed to Study the Distortion of Light by Underwater Microstructure Fluctuations

    DTIC Science & Technology

    2015-05-11

    turbulence environment allowing the variation of turbulence intensity. Convective turbulence is generated in a large Rayleigh-Bénard type tank (5m by...energy and temperature variance dissipation rates in the tank, for different convective strengths. Optical image degradation in the tank is then...dynamics simulations of convective turbulence emulating the tank environment. These numerical simulations supplement the sparse laboratory measurements

  1. [High Pressure Gas Tanks

    NASA Technical Reports Server (NTRS)

    Quintana, Rolando

    2002-01-01

    Four high-pressure gas tanks, the basis of this study, were especially made by a private contractor and tested before being delivered to NASA Kennedy Space Center. In order to insure 100% reliability of each individual tank the staff at KSC decided to again submit the four tanks under more rigorous tests. These tests were conducted during a period from April 10 through May 8 at KSC. This application further validates the predictive safety model for accident prevention and system failure in the testing of four high-pressure gas tanks at Kennedy Space Center, called Continuous Hazard Tracking and Failure Prediction Methodology (CHTFPM). It is apparent from the variety of barriers available for a hazard control that some barriers will be more successful than others in providing protection. In order to complete the Barrier Analysis of the system, a Task Analysis and a Biomechanical Study were performed to establish the relationship between the degree of biomechanical non-conformities and the anomalies found within the system on particular joints of the body. This relationship was possible to obtain by conducting a Regression Analysis to the previously generated data. From the information derived the body segment with the lowest percentage of non-conformities was the neck flexion with 46.7%. Intense analysis of the system was conducted including Preliminary Hazard Analysis (PHA), Failure Mode and Effect Analysis (FMEA), and Barrier Analysis. These analyses resulted in the identification of occurrences of conditions, which may be becoming hazardous in the given system. These conditions, known as dendritics, may become hazards and could result in an accident, system malfunction, or unacceptable risk conditions. A total of 56 possible dendritics were identified. Work sampling was performed to observe the occurrence each dendritic. The out of control points generated from a Weighted c control chart along with a Pareto analysis indicate that the dendritics "Personnel not

  2. Improved Tank Testing Methods

    DTIC Science & Technology

    1980-01-01

    slowly. During the final tests, the tank is inspected for leaks and also signs of “distress” in the shell. All detected leaks are repaired. Manufacturers...capillary action. Penetrant inspection is widely used in the fabrication industries for the detection of There are two basic types of penetrants, one is a...4 in. of the leak to be detected . If the weld being inspected is wider than 1/4 in. two parallel passes must be made to ensure that all leaks are

  3. Tank Waste Remediation System Tank Waste Analysis Plan. FY 1995

    SciTech Connect

    Haller, C.S.; Dove, T.H.

    1994-11-01

    This documents lays the groundwork for preparing the implementing the TWRS tank waste analysis planning and reporting for Fiscal Year 1995. This Tank Waste Characterization Plan meets the requirements specified in the Hanford Federal Facility Agreement and Consent Order, better known as the Tri-Party Agreement.

  4. 39. DIABLO POWERHOUSE: GRAVITY LUBRICATING OIL TANKS. THESE TANKS ARE ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    39. DIABLO POWERHOUSE: GRAVITY LUBRICATING OIL TANKS. THESE TANKS ARE LOCATED AT ROOF LEVEL AT THE NORTHEAST REAR CORNER OF DIABLO POWERHOUSE, 1989. - Skagit Power Development, Diablo Powerhouse, On Skagit River, 6.1 miles upstream from Newhalem, Newhalem, Whatcom County, WA

  5. Characterization of DWPF recycle condensate tank materials

    SciTech Connect

    Bannochie, C. J.

    2015-01-01

    A Defense Waste Processing Facility (DWPF) Recycle Condensate Tank (RCT) sample was delivered to the Savannah River National Laboratory (SRNL) for characterization with particular interest in the concentration of I-129, U-233, U-235, total U, and total Pu. Since a portion of Salt Batch 8 will contain DWPF recycle materials, the concentration of I-129 is important to undertand for salt batch planning purposes. The chemical and physical characterizations are also needed as input to the interpretation of future work aimed at determining the propensity of the RCT material to foam, and methods to remediate any foaming potential. According to DWPF the Tank Farm 2H evaporator has experienced foaming while processing DWPF recycle materials. The characterization work on the RCT samples has been completed and is reported here. The composition of the Sludge Batch 8 (SB8) RCT material is largely a low base solution of 0.2M NaNO2 and 0.1M NaNO3 with a small amount of formate present. Insoluble solids comprise only 0.05 wt.% of the slurry. The solids appear to be largely sludge-like solids based on elemental composition and SEM-EDS analysis. The sample contains an elevated concentration of I-129 (38x) and substantial 59% fraction of Tc-99, as compared to the incoming SB8 Tank 40 feed material. The Hg concentration is 5x, when compared to Fe, of that expected based on sludge carryover. The total U and Pu concentrations are reduced significantly, 0.536 wt.% TS and 2.42E-03 wt.% TS, respectively, with the fissile components, U-233, U-235, Pu-239, and Pu-241, an order of magnitude lower in concentration than those in the SB8 Tank 40 DWPF feed material. This report will be revised to include the foaming study requested in the TTR and outlined in the TTQAP when that work is concluded.

  6. EXPERIMENTAL METHODS TO ESTIMATE ACCUMULATED SOLIDS IN NUCLEAR WASTE TANKS

    SciTech Connect

    Duignan, M.; Steeper, T.; Steimke, J.

    2012-12-10

    The Department of Energy has a large number of nuclear waste tanks. It is important to know if fissionable materials can concentrate when waste is transferred from staging tanks prior to feeding waste treatment plants. Specifically, there is a concern that large, dense particles, e.g., plutonium containing, could accumulate in poorly mixed regions of a blend tank heel for tanks that employ mixing jet pumps. At the request of the DOE Hanford Tank Operations Contractor, Washington River Protection Solutions, the Engineering Development Laboratory of the Savannah River National Laboratory performed a scouting study in a 1/22-scale model of a waste tank to investigate this concern and to develop measurement techniques that could be applied in a more extensive study at a larger scale. Simulated waste tank solids and supernatant were charged to the test tank and rotating liquid jets were used to remove most of the solids. Then the volume and shape of the residual solids and the spatial concentration profiles for the surrogate for plutonium were measured. This paper discusses the overall test results, which indicated heavy solids only accumulate during the first few transfer cycles, along with the techniques and equipment designed and employed in the test. Those techniques include: Magnetic particle separator to remove stainless steel solids, the plutonium surrogate from a flowing stream; Magnetic wand used to manually remove stainless steel solids from samples and the tank heel; Photographs were used to determine the volume and shape of the solids mounds by developing a composite of topographical areas; Laser rangefinders to determine the volume and shape of the solids mounds; Core sampler to determine the stainless steel solids distribution within the solids mounds; Computer driven positioner that placed the laser rangefinders and the core sampler over solids mounds that accumulated on the bottom of a scaled staging tank in locations where jet velocities were low. These

  7. SINDA/FLUINT Stratified Tank Modeling for Cryrogenic Propellant Tanks

    NASA Technical Reports Server (NTRS)

    Sakowski, Barbara

    2014-01-01

    A general purpose SINDA/FLUINT (S/F) stratified tank model was created to simulate self-pressurization and axial jet TVS; Stratified layers in the vapor and liquid are modeled using S/F lumps.; The stratified tank model was constructed to permit incorporating the following additional features:, Multiple or singular lumps in the liquid and vapor regions of the tank, Real gases (also mixtures) and compressible liquids, Venting, pressurizing, and draining, Condensation and evaporation/boiling, Wall heat transfer, Elliptical, cylindrical, and spherical tank geometries; Extensive user logic is used to allow detailed tailoring - Don't have to rebuilt everything from scratch!!; Most code input for a specific case is done through the Registers Data Block:, Lump volumes are determined through user input:; Geometric tank dimensions (height, width, etc); Liquid level could be input as either a volume percentage of fill level or actual liquid level height

  8. Program plan for evaluation and remediation of the generation and release of flammable gases in Hanford Site waste tanks

    SciTech Connect

    Johnson, G.D.

    1991-08-01

    This program plan describes the activities being conducted for the resolution of the flammable gas problem that is associated with 23 high-level waste tanks at the Hanford Site. The classification of the wastes in all of these tanks is not final and some wastes may not be high-level wastes. However, until the characterization and classification is complete, all the tanks are treated as if they contain high-level waste. Of the 23 tanks, Tank 241-SY-101 (referred to as Tank 101-SY) has exhibited significant episodic releases of flammable gases (hydrogen and nitrous oxide) for the past 10 years. The major near-term focus of this program is for the understanding and stabilization of this tank. An understanding of the mechanism for gas generation and the processes for the episodic release will be obtained through sampling of the tank contents, laboratory studies, and modeling of the tank behavior. Additional information will be obtained through new and upgraded instrumentation for the tank. A number of remediation, or stabilization, concepts will be evaluated for near-term (2 to 3 years) applications to Tank 101-SY. Detailed safety assessments are required for all activities that will occur in the tank (sampling, removal of equipment, and addition of new instruments). This program plan presents a discussion of each task, provides schedules for near-term activities, and gives a summary of the expected work for fiscal years 1991, 1992, and 1993. 16 refs., 7 figs., 8 tabs.

  9. TFA Tank Focus Area - multiyear program plan FY98-FY00

    SciTech Connect

    1997-09-01

    The U.S. Department of Energy (DOE) continues to face a major radioactive waste tank remediation problem with hundreds of waste tanks containing hundreds of thousands of cubic meters of high-level waste (HLW) and transuranic (TRU) waste across the DOE complex. Approximately 80 tanks are known or assumed to have leaked. Some of the tank contents have reacted to form flammable gases, introducing additional safety risks. These tanks must be maintained in a safe condition and eventually remediated to minimize the risk of waste migration and/or exposure to workers, the public, and the environment. However, programmatic drivers are more ambitious than baseline technologies and budgets will support. Science and technology development investments are required to reduce the technical and programmatic risks associated with the tank remediation baselines. The Tanks Focus Area (TFA) was initiated in 1994 to serve as the DOE`s Office of Environmental Management`s (EM`s) national technology development program for radioactive waste tank remediation. The national program was formed to increase integration and realize greater benefits from DOE`s technology development budget. The TFA is responsible for managing, coordinating, and leveraging technology development to support DOE`s four major tank sites: Hanford Site (Washington), Idaho National Engineering and Environmental Laboratory (INEEL) (Idaho), Oak Ridge Reservation (ORR) (Tennessee), and Savannah River Site (SRS) (South Carolina). Its technical scope covers the major functions that comprise a complete tank remediation system: waste retrieval, waste pretreatment, waste immobilization, tank closure, and characterization of both the waste and tank with safety integrated into all the functions. The TFA integrates program activities across organizations that fund tank technology development EM, including the Offices of Waste Management (EM-30), Environmental Restoration (EM-40), and Science and Technology (EM-50).

  10. West Valley Tank 8D-1 and 8D-2 Inventory Estimation Methodology

    SciTech Connect

    O'Brien, Robert F.; Heasler, Patrick G.; Rowell, Laurene

    2001-07-20

    This report details work funded by the West Valley Support Project (WVSP) and the Tanks Focus Area Retrieval and Closure Program. The work was conducted by the Pacific Northwest National Laboratory (PNNL) and is in support of the West Valley Demonstration Project (WVDP). The WVDP site in New York was originally the site of a commercial nuclear fuel reprocessing plant. The high-level waste (HLW), approximately 2 million liters, produced during plutonium-uranium extraction (PUREX) and thorium extraction (THOREX) reprocessing campaigns at the plant and subsequent HLW preprocessing, was stored on site in three tanks identified as 8D-1, 8D-2, and 8D-4. Waste from the PUREX process was neutralized with NaOH for storage in a carbon steel tank designated as 8D-2. Neutralization resulted in a precipitated hydroxide sludge that settled to the bottom of the tank and was covered by a supernatant salt solution. The acidic THOREX waste, approximately 55,000 L, was first stored in a stainless steel tank (8D-4) and then added to the PUREX waste in Tank 8D-2. Supernatant decontamination, primarily cesium removal, was conducted by ion-exchange using in-tank columns suspended in Tank 8D-1. The cesium-loaded zeolite, resulting from the supernatant decontamination process, was dumped to the bottom of Tank 8D-1. Approximately 90% of the spent zeolite was transferred from Tank 8D-1 into Tank 8D-2 by the start of vitrification processing in June 1996. Periodically, the remaining spent zeolite contained in Tank 8D-1 is incrementally transferred to 8D-2. The combined waste in Tank 8D-2 continues to be processed through the Vitrification Facility into canisters for final repository disposal.

  11. TFA Tanks Focus Area Multiyear Program Plan FY00-FY04

    SciTech Connect

    BA Carteret; JH Westsik; LR Roeder-Smith; RL Gilchrist; RW Allen; SN Schlahta; TM Brouns

    1999-10-12

    The U.S. Department of Energy (DOE) continues to face a major radioactive waste tank remediation problem with hundreds of waste tanks containing hundreds of thousands of cubic meters of high-level waste (HLW) and transuranic (TRU) waste across the DOE complex. Approximately 68 tanks are known or assumed to have leaked contamination to the soil. Some of the tank contents have reacted to form flammable gases, introducing additional safety risks. These tanks must be maintained in a safe condition and eventually remediated to minimize the risk of waste migration and/or exposure to workers, the public, and the environment. However, programmatic drivers are more ambitious than baseline technologies and budgets will support. Science and technology development investments are required to reduce the technical and programmatic risks associated with the tank remediation baselines. The Tanks Focus Area (TFA) was initiated in 1994 to serve as the DOE Office of Environmental Management's (EM's) national technology development program. for radioactive waste tank remediation. The national program was formed to increase integration and realize greater benefits from DOE's technology development budget. The TFA is responsible for managing, coordinating, and leveraging technology development to support DOE's five major tank sites: Hanford Site (Washington), Idaho National Engineering and Environmental Laboratory (INEEL) (Idaho), Oak Ridge Reservation (ORR) (Tennessee), Savannah River Site (SRS) (South Carolina), and West Valley Demonstration Project (WVDP) (New York). Its technical scope covers the major functions that comprise a complete tank remediation system: waste retrieval, waste pretreatment, waste immobilization, tank closure, and characterization of both the waste and tank with safety integrated into all the functions. The TFA integrates program activities across EM organizations that fund tank technology development, including the Offices of Waste Management (EM-30

  12. In-Tank Precipitation Facility (ITP) and H-Tank Farm (HTF) geotechnical report, WSRC-TR-95-0057, Revision 0, Volume 3

    SciTech Connect

    Fisk, B.E.; Timian, D.A.

    1995-06-02

    A geotechnical study has been completed in H-Area for the In-Tank Precipitation Facility (ITP) and the balance of the H-Area Tank Farm (HTF) at the Savannah River Site (SRS) in South Carolina. The study consisted of subsurface field exploration, field and laboratory testing, and engineering analyses. The purpose of these investigations is to evaluate the overall stability of the H-Area tanks under static and dynamic conditions. The objectives of the study are to define the site-specific geological conditions at ITP and HTF, obtain engineering properties for the assessment of the stability of the native soils and embankment under static and dynamic loads (i.e., slope stability, liquefaction potential, and potential settlements), and derive properties for soil-structure interaction studies. This document contains the records of cone penetrometer and dilatometer soundings for the In-Tank Precipitation Facility (ITP) and H-Tank Farm (HTF) Geotechnical Report, Volume 3.

  13. Analysis of the Tank 6F Final Characterization Samples-2012

    SciTech Connect

    Oji, L. N.; Diprete, D. P.; Coleman, C. J.; Hay, M. S.; Shine, E. P.

    2013-01-31

    The Savannah River National Laboratory (SRNL) was requested by Savannah River Remediation (SRR) to provide sample preparation and analysis of the Tank 6F final characterization samples to determine the residual tank inventory prior to grouting. Fourteen residual Tank 6F solid samples from three areas on the floor of the tank were collected and delivered to SRNL between May and August 2011. These Tank 6F samples were homogenized and combined into three composite samples based on a proportion compositing scheme and the resulting composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 6F composite samples include bulk density and water leaching of the solids to account for water soluble components. The composite Tank 6F samples were analyzed and the data reported in triplicate. Sufficient quality assurance standards and blanks were utilized to demonstrate adequate characterization of the Tank 6F samples. The main evaluation criteria were target detection limits specified in the technical task request document. While many of the target detection limits were met for the species characterized for Tank 6F some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The isotopes whose detection limits were not met in all cases included Sn-126, Sb-126, Sb-126m, Eu-152, Cm- 243 and Cf-249. SRNL, in conjunction with the customer, reviewed all of these cases and determined that the impacts of not meeting the target detection limits were acceptable. Based on the analyses of variance (ANOVA) for the inorganic constituents of Tank 6F, all the inorganic constituents displayed heterogeneity. The inorganic results demonstrated consistent differences across the composite samples: lowest concentrations for Composite Sample 1, intermediate-valued concentrations for Composite

  14. ANALYSIS OF THE TANK 6F FINAL CHARACTERIZATION SAMPLES-2012

    SciTech Connect

    Oji, L.; Diprete, D.; Coleman, C.; Hay, M.; Shine, G.

    2012-06-28

    The Savannah River National Laboratory (SRNL) was requested by Savannah River Remediation (SRR) to provide sample preparation and analysis of the Tank 6F final characterization samples to determine the residual tank inventory prior to grouting. Fourteen residual Tank 6F solid samples from three areas on the floor of the tank were collected and delivered to SRNL between May and August 2011. These Tank 6F samples were homogenized and combined into three composite samples based on a proportion compositing scheme and the resulting composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 6F composite samples include bulk density and water leaching of the solids to account for water soluble components. The composite Tank 6F samples were analyzed and the data reported in triplicate. Sufficient quality assurance standards and blanks were utilized to demonstrate adequate characterization of the Tank 6F samples. The main evaluation criteria were target detection limits specified in the technical task request document. While many of the target detection limits were met for the species characterized for Tank 6F some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The isotopes whose detection limits were not met in all cases included Sn-126, Sb-126, Sb-126m, Eu-152, Cm-243 and Cf-249. SRNL, in conjunction with the customer, reviewed all of these cases and determined that the impacts of not meeting the target detection limits were acceptable. Based on the analyses of variance (ANOVA) for the inorganic constituents of Tank 6F, all the inorganic constituents displayed heterogeneity. The inorganic results demonstrated consistent differences across the composite samples: lowest concentrations for Composite Sample 1, intermediate-valued concentrations for Composite

  15. Analysis Of The Tank 6F Final Characterization Samples-2012

    SciTech Connect

    Oji, L. N.; Diprete, D. P.; Coleman, C. J.; Hay, M. S.; Shine, E. P.

    2012-09-27

    The Savannah River National Laboratory (SRNL) was requested by Savannah River Remediation (SRR) to provide sample preparation and analysis of the Tank 6F final characterization samples to determine the residual tank inventory prior to grouting. Fourteen residual Tank 6F solid samples from three areas on the floor of the tank were collected and delivered to SRNL between May and August 2011. These Tank 6F samples were homogenized and combined into three composite samples based on a proportion compositing scheme and the resulting composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 6F composite samples include bulk density and water leaching of the solids to account for water soluble components. The composite Tank 6F samples were analyzed and the data reported in triplicate. Sufficient quality assurance standards and blanks were utilized to demonstrate adequate characterization of the Tank 6F samples. The main evaluation criteria were target detection limits specified in the technical task request document. While many of the target detection limits were met for the species characterized for Tank 6F some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The isotopes whose detection limits were not met in all cases included Sn-126, Sb-126, Sb-126m, Eu-152, Cm-243 and Cf-249. SRNL, in conjunction with the customer, reviewed all of these cases and determined that the impacts of not meeting the target detection limits were acceptable. Based on the analyses of variance (ANOVA) for the inorganic constituents of Tank 6F, all the inorganic constituents displayed heterogeneity. The inorganic results demonstrated consistent differences across the composite samples: lowest concentrations for Composite Sample 1, intermediate-valued concentrations for Composite

  16. Tanks Focus Area site needs assessment FY 2000

    SciTech Connect

    RW Allen

    2000-04-11

    This report documents the process used by the Tanks Focus Area (TFA) to analyze and develop responses to technology needs submitted by five major U.S. Department of Energy (DOE) sites with radioactive tank waste problems, and the initial results of the analysis. The sites are the Hanford Site, Idaho National Engineering and Environmental Laboratory (INEEL), Oak Ridge Reservation (ORR), Savannah River Site (SRS), and West Valley Demonstration Project (WVDP). During the past year, the TFA established a link with DOE's Fernald site to exchange, on a continuing basis, mutually beneficial technical information and assistance.

  17. Design and Implementation of the MSL Cruise Propulsion Tank Heaters

    NASA Technical Reports Server (NTRS)

    Krylo, Robert; Mikhaylov, Rebecca; Cucullu, Gordon; Watkins, Brenda

    2008-01-01

    This slide presentation reviews the design and the implementation of the heaters for the Mars Science Laboratory (MSL). The pressurized tanks store hydrazine that freezes at 2 C, this means that heaters are required to keep the hydrazine and the helium at 36 C for the trip to Mars. Using the TMG software the heat loss was analyzed, and a thermal model simulates a half full tank which yielded a 13W heating requirement for each hemisphere. Views of the design, and the heater are included.

  18. PILOT-SCALE TESTING OF THE SUSPENSION OF MST, CST, AND SIMULATED SLUDGE SLURRIES IN A SLUDGE TANK

    SciTech Connect

    Poirier, M.; Qureshi, Z.; Restivo, M.; Steeper, T.; Williams, M.; Herman, D.

    2011-08-02

    The Small Column Ion Exchange (SCIX) process is being developed to remove cesium, strontium, and actinides from Savannah River Site (SRS) Liquid Waste using an existing waste tank (i.e., Tank 41H) to house the process. Following strontium, actinide, and cesium removal, the concentrated solids will be transported to a sludge tank (i.e., monosodium titanate (MST)/sludge solids to Tank 42H or Tank 51H and crystalline silicotitanate (CST) to Tank 40H) for eventual transfer to the Defense Waste Processing Facility (DWPF). Savannah River National Laboratory (SRNL) is conducting pilot-scale mixing tests to determine the pump requirements for mixing MST, CST, and simulated sludge. The purpose of this pilot scale testing is to determine the pump requirements for mixing MST and CST with sludge in a sludge tank and to determine whether segregation of particles occurs during settling. Tank 40H and Tank 51H have four Quad Volute pumps; Tank 42H has four standard pumps. The pilot-scale tank is a 1/10.85 linear scaled model of Tank 40H. The tank diameter, tank liquid level, pump nozzle diameter, pump elevation, and cooling coil diameter are all 1/10.85 of their dimensions in Tank 40H. The pump locations correspond to the current locations in Tank 40H (Risers B2, H, B6, and G). The pumps are pilot-scale Quad Volute pumps. Additional settling tests were conducted in a 30 foot tall, 4 inch inner diameter clear column to investigate segregation of MST, CST, and simulated sludge particles during settling.

  19. Concrete material characterization reinforced concrete tank structure Multi-Function Waste Tank Facility

    NASA Astrophysics Data System (ADS)

    Winkel, B. V.

    1995-03-01

    The purpose of this report is to document the Multi-Function Waste Tank Facility (MWTF) Project position on the concrete mechanical properties needed to perform design/analysis calculations for the MWTF secondary concrete structure. This report provides a position on MWTF concrete properties for the Title 1 and Title 2 calculations. The scope of the report is limited to mechanical properties and does not include the thermophysical properties of concrete needed to perform heat transfer calculations. In the 1970's, a comprehensive series of tests were performed at Construction Technology Laboratories (CTL) on two different Hanford concrete mix designs. Statistical correlations of the CTL data were later generated by Pacific Northwest Laboratories (PNL). These test results and property correlations have been utilized in various design/analysis efforts of Hanford waste tanks. However, due to changes in the concrete design mix and the lower range of MWTF operating temperatures, plus uncertainties in the CTL data and PNL correlations, it was prudent to evaluate the CTL data base and PNL correlations, relative to the MWTF application, and develop a defendable position. The CTL test program for Hanford concrete involved two different mix designs: a 3 kip/sq in mix and a 4.5 kip/sq in mix. The proposed 28-day design strength for the MWTF tanks is 5 kip/sq in. In addition to this design strength difference, there are also differences between the CTL and MWTF mix design details. Also of interest, are the appropriate application of the MWTF concrete properties in performing calculations demonstrating ACI Code compliance. Mix design details and ACI Code issues are addressed in Sections 3.0 and 5.0, respectively. The CTL test program and PNL data correlations focused on a temperature range of 250 to 450 F. The temperature range of interest for the MWTF tank concrete application is 70 to 200 F.

  20. Concrete material characterization reinforced concrete tank structure Multi-Function Waste Tank Facility

    SciTech Connect

    Winkel, B.V.

    1995-03-03

    The purpose of this report is to document the Multi-Function Waste Tank Facility (MWTF) Project position on the concrete mechanical properties needed to perform design/analysis calculations for the MWTF secondary concrete structure. This report provides a position on MWTF concrete properties for the Title 1 and Title 2 calculations. The scope of the report is limited to mechanical properties and does not include the thermophysical properties of concrete needed to perform heat transfer calculations. In the 1970`s, a comprehensive series of tests were performed at Construction Technology Laboratories (CTL) on two different Hanford concrete mix designs. Statistical correlations of the CTL data were later generated by Pacific Northwest Laboratories (PNL). These test results and property correlations have been utilized in various design/analysis efforts of Hanford waste tanks. However, due to changes in the concrete design mix and the lower range of MWTF operating temperatures, plus uncertainties in the CTL data and PNL correlations, it was prudent to evaluate the CTL data base and PNL correlations, relative to the MWTF application, and develop a defendable position. The CTL test program for Hanford concrete involved two different mix designs: a 3 kip/in{sup 2} mix and a 4.5 kip/in{sup 2} mix. The proposed 28-day design strength for the MWTF tanks is 5 kip/in{sup 2}. In addition to this design strength difference, there are also differences between the CTL and MWTF mix design details. Also of interest, are the appropriate application of the MWTF concrete properties in performing calculations demonstrating ACI Code compliance. Mix design details and ACI Code issues are addressed in Sections 3.0 and 5.0, respectively. The CTL test program and PNL data correlations focused on a temperature range of 250 to 450 F. The temperature range of interest for the MWTF tank concrete application is 70 to 200 F.

  1. Tank Vapor Characterization Project: Headspace vapor characterization of Hanford Waste Tank U-204, Results from samples collected on August 8, 1995

    SciTech Connect

    Clauss, T.W.; Evans, J.C.; McVeety, B.D.; Pool, K.H.; Thomas, B.L.; Olsen, K.B.; Fruchter, J.S.; Ligotke, M.W.

    1995-11-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-U-204 (Tank U-204) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank-farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNL. Analyte concentrations were based on analytical results and, where appropriate, sample volumes provided by WHC. A summary of the results is listed. Detailed descriptions of the analytical results appear in the text.

  2. Tank Vapor Characterization Project. Headspace vapor characterization of Hanford Waste Tank AX-102: Results from samples collected on June 27, 1995

    SciTech Connect

    Clauss, T.W.; Pool, K.H.; Evans, J.C.; McVeety, B.D.; Thomas, B.L.; Olsen, K.B.; Fruchter, J.S.; Ligotke, M.W.

    1995-11-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-AX-102 (Tank AX-102) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank-farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest Laboratory (PNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNL. Analyte concentrations were based on analytical results and, where appropriate, sample volumes provided by WHC. Detailed descriptions of the analytical results appear in the text.

  3. Tank vapor characterization project - Tank 241-U-112 headspace gas and vapor characterization: Results for homogeneity samples collected on December 6, 1996

    SciTech Connect

    Sklarew, D.S.; Pool, K.H.; Evans, J.C.; Hayes, J.C.

    1997-09-01

    This report presents the results of analyses of samples taken from the headspace of waste storage tank 241-U-112 (Tank U-112) at the Hanford Site in Washington State. Samples were collected to determine the homogeneity of selected inorganic and organic headspace constitutents. Two risers (Riser 3 and Riser 6) were sampled at three different elevations (Bottom, Middle, and Top) within the tank. Tank headspace samples were collected by SGN Eurisys Service Corporation (SESC) and were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Ammonia was determined to be above the immediate notification limit specified by the sampling and analysis plan.

  4. Tank Vapor Characterization Project: Headspace vapor characterization of Hanford Waste Tank U-203, Results from samples collected on August 8, 1995

    SciTech Connect

    Pool, K.H.; Clauss, T.W.; Evans, J.C.; McVeety, B.D.; Thomas, B.L.; Olsen, K.B.; Fruchter, J.S.; Ligotke, M.W.

    1995-11-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-U-203 (Tank U-203) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank-farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest Laboratory (PNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNL. Analyte concentrations were based on analytical results and, where appropriate, sample volumes provided by WHC. A summary of the results is listed. Detailed descriptions of the analytical results appear in the text.

  5. Tank Vapor Characterization Project: Headspace vapor characterization of Hanford Waste Tank 241-S-109: Results from samples collected on 06/04/96

    SciTech Connect

    Pool, K.H.; Thomas, B.L.; Evans, J.C.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-S-109 (Tank S-109) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, on sample volumes provided by WHC. A summary of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed in Table S.1. Detailed descriptions of the analytical results appear in the appendices.

  6. Tank Vapor Characterization Project: Headspace vapor characterization of Hanford Waste Tank 241-BX-105: Results from samples collected on 04/24/96

    SciTech Connect

    Thomas, B.L.; Evans, J.C.; Pool, K.H.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-BX-105 (Tank BX-105) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, on sample volumes provided by WHC. A summary of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed in Table S.1. Detailed descriptions of the analytical results appear in the appendices.

  7. Tank Vapor Characterization Project: Headspace vapor characterization of Hanford Tank 241-S-107: Results from samples collected on 06/18/96

    SciTech Connect

    Pool, K.H.; Evans, J.C.; Thomas, B.L.

    1997-01-01

    This report describes the analytical results of vapor samples taken from the headspace of the waste storage tank 241-S-107 (Tank S-107) at the Hanford Site in Washington State. The results described in this report were obtained to characterize the vapors present in the tank headspace and to support safety evaluations and tank farm operations. The results include air concentrations of selected inorganic and organic analytes and grouped compounds from samples obtained by Westinghouse Hanford Company (WHC) and provided for analysis to Pacific Northwest National. Laboratory (PNNL). Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. Analyte concentrations were based on analytical results and, where appropriate, on sample volumes provided by WHC. A summary of the inorganic analytes, permanent gases, and total non-methane organic compounds is listed in Table S.1. Detailed descriptions of the analytical results appear in the appendices.

  8. Tank vapor characterization project - Tank 241-TY-103 headspace gas and vapor characterization: Results for homogeneity samples collected on November 22, 1996

    SciTech Connect

    Olsen, K.B.; Pool, K.H.; Evans, J.C.; Hayes, J.C.

    1997-07-01

    This report presents the results of analyses of samples taken from the headspace of waste storage tank 241-TY-103 (Tank TY-103) at the Hanford Site in Washington State. Samples were collected to determine the homogeneity of selected inorganic and organic headspace constituents. Two risers (Riser 8 and Riser 18) were sampled at three different elevations (Top, Middle, and Bottom) within the tank. Tank headspace samples were collected by SGN Eurisys Service Corporation (SESC) and were analyzed by Pacific Northwest National Laboratory (PNNL) to determine headspace concentrations of selected non-radioactive analytes. Analyses were performed by the Vapor Analytical Laboratory (VAL) at PNNL. No analytes were determined to be above immediate notification limits specified by the sampling and analysis plan (SAP).

  9. Sampling and analysis plan for site assessment during the closure or replacement of nonradioactive underground storage tanks

    SciTech Connect

    Gitt, M.J.

    1990-08-01

    The Tank Management Program is responsible for closure or replacement of nonradioactive underground storage tanks throughout the Idaho National Engineering Laboratory (INEL). A Sampling and Analysis Plan (SAP) has been developed that complies with EPA regulations and with INEL Tank Removal Procedures for sampling activities associated with site assessment during these closure or replacement activities. The SAP will ensure that all data are valid, and it also will function as a Quality Assurance Project Plan. 18 refs., 8 figs., 11 tabs.

  10. ALUMINUM REMOVAL AND SODIUM HYDROXIDE REGENERATION FROM HANFORD TANK WASTE BY LITHIUM HYDROTALCITE PRECIPITATION SUMMARY OF PRIOR LAB-SCALE TESTING

    SciTech Connect

    SAMS TL; GUILLOT S

    2011-01-27

    Scoping laboratory scale tests were performed at the Chemical Engineering Department of the Georgia Institute of Technology (Georgia Tech), and the Hanford 222-S Laboratory, involving double-shell tank (DST) and single-shell tank (SST) Hanford waste simulants. These tests established the viability of the Lithium Hydrotalcite precipitation process as a solution to remove aluminum and recycle sodium hydroxide from the Hanford tank waste, and set the basis of a validation test campaign to demonstrate a Technology Readiness Level of 3.

  11. Tank 241-AX-104 upper vadose zone cone penetrometer demonstration sampling and analysis plan

    SciTech Connect

    FIELD, J.G.

    1999-02-02

    This sampling and analysis plan (SAP) is the primary document describing field and laboratory activities and requirements for the tank 241-AX-104 upper vadose zone cone penetrometer (CP) demonstration. It is written in accordance with Hanford Tank Initiative Tank 241-AX-104 Upper Vadose Zone Demonstration Data Quality Objective (Banning 1999). This technology demonstration, to be conducted at tank 241-AX-104, is being performed by the Hanford Tanks Initiative (HTI) Project as a part of Tank Waste Remediation System (TWRS) Retrieval Program (EM-30) and the Office of Science and Technology (EM-50) Tanks Focus Area. Sample results obtained as part of this demonstration will provide additional information for subsequent revisions to the Retrieval Performance Evaluation (RPE) report (Jacobs 1998). The RPE Report is the result of an evaluation of a single tank farm (AX Tank Farm) used as the basis for demonstrating a methodology for developing the data and analyses necessary to support making tank waste retrieval decisions within the context of tank farm closure requirements. The RPE includes a study of vadose zone contaminant transport mechanisms, including analysis of projected tank leak characteristics, hydrogeologic characteristics of tank farm soils, and the observed distribution of contaminants in the vadose zone in the tank farms. With limited characterization information available, large uncertainties exist as to the nature and extent of contaminants that may exist in the upper vadose zone in the AX Tank Farm. Traditionally, data has been collected from soils in the vadose zone through the installation of boreholes and wells. Soil samples are collected as the bore hole is advanced and samples are screened on site and/or sent to a laboratory for analysis. Some in-situ geophysical methods of contaminant analysis can be used to evaluate radionuclide levels in the soils adjacent to an existing borehole. However, geophysical methods require compensation for well

  12. FY 1999 Cold Demonstration of the Multi-Point Injection (MPI ) Process for Stabilizing Contaminated Sludge in Buried Horizontal Tanks with Limited Access at the Oak Ridge National Laboratory and Savannah River Site

    SciTech Connect

    Kauschinger, J.L.

    2000-02-04

    Operations at U.S. Department of Energy (DOE) sites, such as Oak Ridge National Laboratory (ORNL) and Savannah River Site (SRS), have generated a variety of waste streams that have resulted in releases to the environment. These releases have created areas or suspected areas of contamination and contaminated facilities that could contain hazardous, radioactive, and/or mixed wastes. As a result, these areas or facilities are subject to environmental assessments and possible restoration, primarily under the provisions of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and the Resource Conservation and Recovery Act (RCRA). To reduce risks to human health and the environment and to comply with the requirements of the various environmental laws and regulations, multidisciplinary environmental restoration (ER) programs [which include remedial actions and decontamination and decommissioning and waste management programs] have been established to identify, characterize, and remediate sites and facilities at both ORNL and SRS. To coordinate and ensure compliance with the applicable laws and regulations, DOE, the U.S. Environmental Protection Agency (EPA) regions, and the respective state environmental agencies have entered into Federal Facilities Compliance Agreements (FFCA) and/or Consent Agreements. The Environmental Management, Office of Technology Development, and other agencies provide needed technology development and demonstration support for ER programs. The work described in this report is an illustration of the cooperation between and among the DOE, Lockheed Martin Energy Research (LMER)--ORNL, Westinghouse--SRS, Bechtel Jacobs Company, and Ground Environmental Services, Inc., (GES), a small business technology provider.

  13. Petroleum storage tank cleaning using commercial microbial culture products

    SciTech Connect

    Schneider, D.R.; Entzeroth, L.C.; Timmis, A.; Whiteside, A.; Hoskins, B.C.

    1995-12-31

    The removal of paraffinic bottom accumulations from refinery storage tanks represents an increasingly costly area of petroleum storage management. Microorganisms can be used to reduce paraffinic bottoms by increasing the solubility of bottom material and by increasing the wax-carrying capacity of carrier oil used in the cleaning process. The economic savings of such treatments are considerable. The process is also intrinsically safer than alternative methods, as it reduces and even eliminates the need for personnel to enter the tank during the cleaning process. Both laboratory and field sample analyses can be used to document changes in tank material during the treatment process. These changes include increases in volatile content and changes in wax distribution. Several case histories illustrating these physical and chemical changes are presented along with the economics of treatment.

  14. Management of petroleum underground storage tanks at the Hanford Site

    SciTech Connect

    Douglas, L.M.; Mihalic, M.A.

    1991-09-01

    This report represents the timetables, responsible organizations, and methods required to comply with the newly promulgated Washington Administrative Code (WAC) 173-360 Underground Storage Tank (UST) Regulations which became effective December 29, 1990. This report only addresses UST systems that contain nonradioactive material. A total of 84 tanks at the Hanford Site are currently regulated under WAC 173-360. In addition, 32 regulated tanks have been removed as a result of the federally mandated program and the newly implemented state regulations. The majority of the USTs at the Hanford Site are operated by Westinghouse Hanford; however, one is operated by Kaiser Engineers Hanford (KEH) and one by Pacific Northwest Laboratory (PNL). 6 refs.

  15. Retainment of the antimicrobial agent triclosan in a septic tank.

    PubMed

    Kirjanova, Ala; Rimeika, Mindaugas; Vollertsen, Jes; Nielsen, Asbjørn Haaning

    2014-01-01

    Laboratory experiments were conducted to investigate the fate of the antimicrobial agent triclosan (TCS) in a conventional septic tank. The main mechanism of TCS removal from wastewater was identified to be rapid TCS sorption to suspended particles followed by settling of these particles to the bottom of the septic tank. Sorption to particles was completed within minutes while the settling took several days. Therefore, in a septic tank the removal of TCS from wastewater is mainly determined by the removal of suspended particles by sedimentation. Over 5 days of hydraulic residence time the initial dissolved TCS concentration of 100 μg L(-1) was reduced by 87 ± 8%. During the first 24 hours, 66-86% of all removed TCS was retained, whereas during the remainder of the experiment a slight but steady decrease in TCS concentration was observed. This was most likely caused by TCS diffusion and its subsequent sorption onto the septic sludge.

  16. Development and Deployment of Advanced Corrosion Monitoring Systems for High-Level Waste Tanks

    SciTech Connect

    Terry, M. T.; Edgemon, G. L.; Mickalonis, J. I.; Mizia, R. E.

    2002-02-26

    This paper describes the results of a collaborative technology development program, sponsored by the Tanks Focus Area, to use electrochemical noise (EN) for corrosion monitoring in underground storage tanks. These tanks, made of carbon or stainless steels, contain high-level radioactive liquid waste (HLW) generated by weapons production or radioactive liquid waste from nuclear fuel reprocessing activities at several Department of Energy (DOE) sites. The term EN is used to describe low frequency fluctuations in current and voltage measurements associated with corrosion. In their most basic form, EN-based corrosion monitoring systems measure and record these fluctuations over time from electrodes immersed in the environment of interest--in this case, radioactive tank waste. The resulting EN signals have characteristic patterns for different corrosion mechanisms. In recent years, engineers and scientists from several DOE sites, in collaboration with several private companies, have conducted laboratory studies and field applications to correlate the EN signals with corrosion mechanisms active in the radioactive waste tanks. The participating DOE sites are Hanford, Savannah River, Oak Ridge Reservation and the Idaho National Engineering and Environmental Laboratory. The commercial vendors have included HiLine Engineering and Fabrication, Inc., EIC Laboratories, Inc., and AEA Technologies. Successful deployment of the EN technology will yield improved information of waste tank corrosion conditions, better tank management, and lower overall cost.

  17. Development and deployment of advanced corrosion monitoring systems for high-level waste tanks.

    SciTech Connect

    Terry, M. T.; Edgemon, G. L.; Mickalonis, J. I.; Mizia, R. E.

    2002-01-01

    This paper describes the results of a collaborative technology development program, sponsored by the Tanks Focus Area, to use electrochemical noise (EN) for corrosion monitoring in underground storage tanks. These tanks, made of carbon or stainless steels, contain high-level radioactive liquid waste (HLW) generated by weapons production or radioactive liquid waste from nuclear fuel reprocessing activities at several Department of Energy (DOE) sites. The term EN is used to describe low frequency fluctuations in current and voltage measurements associated with corrosion. In their most basic form, EN-based corrosion monitoring systems measure and record these fluctuations over time from electrodes immersed in the environment of interest - in this case, radioactive tank waste. The resulting EN signals have characteristic patterns for different corrosion mechanisms. In recent years, engineers and scientists from several DOE sites, in collaboration with several private companies, have conducted laboratory studies and field applications to correlate the EN signals with corrosion mechanisms active in the radioactive waste tanks. The participating DOE sites are Hanford, Savannah River, Oak Ridge Reservation and the Idaho National Engineering and Environmental Laboratory. The commercial vendors have included HiLine Engineering and Fabrication, Inc., EIC Laboratories, Inc., and M A Technologies. Successful deployment of the EN technology will yield improved information of waste tank corrosion conditions, better tank management, and lower overall cost.

  18. Tank farms hazards assessment

    SciTech Connect

    Broz, R.E.

    1994-09-30

    Hanford contractors are writing new facility specific emergency procedures in response to new and revised US Department of Energy (DOE) Orders on emergency preparedness. Emergency procedures are required for each Hanford facility that has the potential to exceed the criteria for the lowest level emergency, an Alert. The set includes: (1) a facility specific procedure on Recognition and Classification of Emergencies, (2) area procedures on Initial Emergency Response and, (3) an area procedure on Protective Action Guidance. The first steps in developing these procedures are to identify the hazards at each facility, identify the conditions that could release the hazardous material, and calculate the consequences of the releases. These steps are called a Hazards Assessment. The final product is a document that is similar in some respects to a Safety Analysis Report (SAR). The document could br produced in a month for a simple facility but could take much longer for a complex facility. Hanford has both types of facilities. A strategy has been adopted to permit completion of the first version of the new emergency procedures before all the facility hazards Assessments are complete. The procedures will initially be based on input from a task group for each facility. This strategy will but improved emergency procedures in place sooner and therefore enhance Hanford emergency preparedness. The purpose of this document is to summarize the applicable information contained within the Waste Tank Facility ``Interim Safety Basis Document, WHC-SD-WM-ISB-001`` as a resource, since the SARs covering Waste Tank Operations are not current in all cases. This hazards assessment serves to collect, organize, document and present the information utilized during the determination process.

  19. Case study to remove radioactive hazardous sludge from long horizontal storage tanks

    SciTech Connect

    Hylton, T.D.; Youngblood, E.L.; Cummins, R.L.

    1995-12-31

    The removal of radioactive hazardous sludge from waste tanks is a significant problem at several US Department of Energy (DOE) sites. The use of submerged jets produced by mixing pumps lowered into the supernatant/sludge interface to produce a homogeneous slurry is being studied at several DOE facilities. The homogeneous slurry can be pumped from the tanks to a treatment facility or alternative storage location. Most of the previous and current studies with this method are for flat-bottom tanks with vertical walls. Because of the difference in geometry, the results of these studies are not directly applicable to long horizontal tanks such as those used at the Oak Ridge National Laboratory. Mobilization and mixing studies were conducted with a surrogate sludge (e.g., kaolin clay) using submerged jets in two sizes of horizontal tanks. The nominal capacities of these tanks were 0.87 m{sup 3} (230 gal) and 95 m{sup 3} (25,000 gal). Mobilization efficiencies and mixing times were determined for single and bidirectional jets in both tanks with the discharge nozzles positioned at two locations in the tanks. Approximately 80% of the surrogate sludge was mobilized in the 95-m{sup 3} tank using a fixed bidirectional jet (inside diameter = 0.035 m) and a jet velocity of 6.4 m/s (21 ft/s).

  20. INVESTIGATING SUSPENSION OF MST SLURRIES IN A PILOT-SCALE WASTE TANK

    SciTech Connect

    Poirier, M.; Restivo, M.; Steeper, T.; Williams, M.; Qureshi, Z.

    2011-01-24

    The Small Column Ion Exchange (SCIX) process is being developed to remove cesium, strontium, and actinides from Savannah River Site (SRS) Liquid Waste using an existing waste tank (i.e., Tank 41H) to house the process. Savannah River National Laboratory (SRNL) is conducting pilot-scale mixing tests to determine the pump requirements for suspending monosodium titanate (MST), crystalline silicotitanate (CST), and simulated sludge. The purpose of this pilot scale testing is for the pumps to suspend the MST particles so that MST can be removed from the tank. The pilot-scale tank is a 1/10.85 linear scaled model of Tank 41H. The tank diameter, tank liquid level, pump nozzle diameter, pump elevation, and cooling coil diameter are all 1/10.85 of their dimensions in Tank 41H. The pump locations correspond to the proposed locations in Tank 41H by the SCIX program (Risers B5 and B2 for two pump configurations and Risers B5, B3, and B1 for three pump configurations).