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Long-term leaching of irradiated spent fuel

Description: Spent Light Water Reactor (LWR) fuel with burnups of 9, 28 and 54 MWd/kg U were leach tested at 25/sup 0/C in deionized water in a Paige apparatus. No discernible differences in leach rates were observed due to burnup. Additionally, the 28 MWd/kg U fuel was IAEA leach tested in five different leachants using the IAEA method. Deionized water gave the highest leach rates and a calcium chloride solution gave the lowest leach rates. An accelerated leaching period was observed during the Paige leach… more
Date: January 1, 1979
Creator: Katayama, Y. B. & Bradley, D. J.
Partner: UNT Libraries Government Documents Department
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Criticality experiments with mixed oxide fuel pin arrays in plutonium-uranium nitrate solution

Description: A series of critical experiments was completed with mixed plutonium-uranium solutions having a Pu/(Pu + U) ratio of approximately 0.22 in a boiler tube-type lattice assembly. These experiments were conducted as part of the Criticality Data Development Program between the United States Department of Energy (USDOE) and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. A complete description of the experiments and data are included in this report. The experiments were perf… more
Date: August 1, 1988
Creator: Lloyd, R.C. (Pacific Northwest Lab., Richland, WA (United States)) & Smolen, G.R. (Oak Ridge National Lab., TN (United States))
Partner: UNT Libraries Government Documents Department
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Hot cell studies of tritium removal from and dissolution of an irradiated thoria fuel

Description: Tritium removal and dissolution studies on an irradiated thoria-based fuel were conducted in the High Level Caves at the Savannah River Laboratory (SRL). The objectives of these studies were to define the effects of key process-related parameters on tritium evolution and subsequent dissolution. The test program at SRL determined the effects on tritium removal of particle size, heating temperature, oxidation, and agitation. ThO/sub 2//UO/sub 2/ (95%/5%) fuel from the Elk River Reactor, irradiate… more
Date: January 1, 1980
Creator: Pickett, J.B.
Partner: UNT Libraries Government Documents Department
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Commercial US nuclear reactors and waste: the current status

Description: Between March 1 and June 15, 1980, the declared size of the commercial light waste reactor (LWR) nuclear power industry in the US has decreased another 9 GWe. For the presently declared size: the 165 declared reactors will peak at a capacity of 153 GWe in 2001 and will consume about 870,000 MTU as enrichment feed; the theoretical rate of enrichment requirements will peak at about 19,000,000 SWUs/y in the year 2014; as few as two repositories each with capacity equivalent to 100,000 MTU would ho… more
Date: September 1, 1980
Creator: Platt, A.M. & Robinson, J.V.
Partner: UNT Libraries Government Documents Department
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DOE Office of Civilian Radioactive Waste Management (OCRWM) system studies digest

Description: The Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) has sponsored system studies to support the evaluation of alternative configurations and operations for the Civilian Radioactive Waste Management System (CRWMS) and the development of system requirements and design specifications. These studies are generally directed toward evaluating the impacts of alternatives to the monitored retrievable storage (MRS) and fuel rod consolidation, waste form and characterist… more
Date: June 1, 1992
Creator: McLeod, N. B. (Johnson and Associates Inc., Fairfax, Virginia (United States)); Nguyen, T. D.; Drexelius, R. (USDOE Office of Civilian Radioactive Waste Management, Washington, DC (United States)) & McKee, R. W. (Pacific Northwest Lab., Richland, WA (United States))
Partner: UNT Libraries Government Documents Department
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Unique sampling and transfer system for the Fluorinel Dissolution and Storage Facility

Description: Liquid sampling, sample transfer and analytical systems for the Fluorinel Dissolution and Storage Facility (FAST) are required for monitoring feed and process solutions on a constant basis during fuel dissolution. Due to sequential batch dissolution, sampling becomes important in monitoring and tracking the dissolution phase of each dissolver. The sampling cell contains 10 liquid samplers, a pneumatic sample transfer sender/receiver, a decontamination service station, plastic transfer capsule c… more
Date: January 1, 1980
Creator: Jacobson, M. E.; Carter, J. A. & Paige, D. M.
Partner: UNT Libraries Government Documents Department
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Consolidated fuel reprocessing. Program progress report, April 1-June 30, 1980

Description: This progress report is compiled from major contributions from three programs: (1) the Advanced Fuel Recycle Program at ORNL; (2) the Converter Fuel Reprocessing Program at Savannah River Laboratory; and (3) the reprocessing components of the HTGR Fuel Recycle Program, primarily at General Atomic and ORNL. The coverage is generally overview in nature; experimental details and data are limited.
Date: September 1, 1980
Partner: UNT Libraries Government Documents Department
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Logistics models for the transportation of radioactive waste and spent fuel

Description: Mathematical modeling of the logistics of waste shipment is an effective way to provide input to program planning and long-range waste management. Several logistics models have been developed for use in parametric studies, contingency planning, and management of transportation networks. These models allow the determination of shipping schedules, optimal routes, probable transportation modes, minimal costs, minimal personnel exposure, minimal transportation equipment, etc. Such information will … more
Date: March 1, 1978
Creator: Joy, D.S. & Holcomb, B.D.
Partner: UNT Libraries Government Documents Department
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Radioactive waste management in the former USSR

Description: Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world's largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems … more
Date: June 1, 1992
Creator: Bradley, D.J.
Partner: UNT Libraries Government Documents Department
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Draft Transportation Institutional Plan

Description: The Department of Energy recognizes that the success of its program to develop and implement a national system for nuclear waste management and disposal depends on broad-based public understanding and acceptance. While each program element has its particular sensitivity, the transportation of the waste may potentially affect the greatest number of people, and accordingly is highly visible and potentially issue-laden. Therefore, the Office of Civilian Radioactive Waste Management has developed t… more
Date: September 1, 1985
Partner: UNT Libraries Government Documents Department
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Application of probabilistic risk assessment to nuclear fuel reprocessing at the Savannah River Plant

Description: The Savannah River Laboratory has developed an integrated risk assessment methodology that has been applied to systems in the nuclear fuel reprocessing facilities at the Savannah River Plant. The methodology can be applied to several types of design and operational problems. Basically, the analysis is subdivided into individual modules that can be either utilized separately or integrated into an overall risk analysis. Computer codes and computer data banks are utilized extensively to minimize t… more
Date: January 1, 1980
Creator: Durant, W S
Partner: UNT Libraries Government Documents Department
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Technical Division quarterly progress report, October 1--December 31, 1977. [Fuel cycle research and development; special materials production]

Description: Results are presented on the fluidized-bed calcination of simulated radioactive waste from the reprocessing of spent commercial nuclear fuel and on the removal of actinide elements from the waste prior to calcination. Other programs include the development of storage technology for /sup 85/Kr waste; and the behavior of volatile radionuclides during the combustion of HTGR graphite-based fuel. The long-term management of defense waste from the ICPP covers post-calcination treatment of ICPP calcin… more
Date: February 1, 1978
Creator: Slansky, C.M. (ed.)
Partner: UNT Libraries Government Documents Department
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Foreign experience on effects of extended dry storage on the integrity of spent nuclear fuel

Description: This report summarizes the results of a survey of foreign experience in dry storage of spent fuel from nuclear power reactors that was carried out for the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The report reviews the mechanisms for degradation of spent fuel cladding and fuel materials in dry storage, identifies the status and plans of world-wide experience and applications, and documents the available information on the expected long-term integr… more
Date: April 1, 1992
Creator: Schneider, K.J. & Mitchell, S.J.
Partner: UNT Libraries Government Documents Department
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Low enrichment fuel conversion for Iowa State University

Description: Work during the reported period was centered primarily in preparation for receiving the LEU fuel and the shipping of the HEU fuel. This included development of procedures and tools for the disassembly process. During the period we held many practice sessions applying these tools and practices to a dummy fuel assembly. The LEU fuel was received on April 10, 1991 and the reactor was shut down on May 3, 1991 for refueling. The twelve HEU fuel assemblies in the UTR-10 reactor core were removed and … more
Date: August 1, 1991
Creator: Rohach, A.F. & Hendrickson, R.A.
Partner: UNT Libraries Government Documents Department
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Disposal of spent fuel

Description: Based on preliminary analyses, spent fuel assemblies are an acceptable form for waste disposal. The following studies appear necessary to bring our knowledge of spent fuel as a final disposal form to a level comparable with that of the solidified wastes from reprocessing: 1. A complete systems analysis is needed of spent fuel disposition from reactor discharge to final isolation in a repository. 2. Since it appears desirable to encase the spent fuel assembly in a metal canister, candidate mater… more
Date: January 1, 1978
Creator: Blomeke, J. O.; Ferguson, D. E. & Croff, A. G.
Partner: UNT Libraries Government Documents Department
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Nondestructive evaluation of LWR spent fuel shipping casks

Description: An analysis of nondestructve testing (NDT) methods currently being used to evaluate the integrity of Light Water Reactor (LWR) spent fuel shipping casks is presented. An assessment of anticipated NDT needs related to breeder reactor cask requirements is included. Specific R and D approaches to probable NDT problem areas such as the evaluation of austenitic stainless steel weldments are outlined. A comprehensive bibliography of current NDT methods for cask evaluation in the USA, Great Britain, J… more
Date: February 1, 1978
Creator: Ballard, D.W.
Partner: UNT Libraries Government Documents Department
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Analysis of Radiation Doses from Operation of Postulated Commercial Spent Fuel Transportation Systems

Description: This report contains a system study of estimated radiation doses to the public and workers resulting from the transport of spent fuel from commercial nuclear power reactors to a geologic repository. The report contains a detailed breakdown of activities and a description of time/distance/dose-rate estimates for each activity within the system. Collective doses are estimated for each of the major activities at the reactor site, in transit, and at the repository receiving facility. Annual individ… more
Date: November 1, 1987
Creator: Schneider, K. J.; Hostick, C. J.; Ross, W. A.; Peterson, R. W.; Smith, R. I.; Stiles, D. L. et al.
Partner: UNT Libraries Government Documents Department
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Assessment of the response of spent fuel transports to malevolent acts

Description: This paper describes the results of a program conducted at Sandia National Laboratories (SNL) for the US Department of Energy to provide an experimental data base for more accurately assessing the radiological consequences from a hypothetical sabotage attack on a spent fuel shipping cask. The primary objectives of the program were limited to: (1) evaluating the effectiveness of selected high explosive devices (HED) in breaching full-size spent fuel casks, (2) quantifying and characterizing rele… more
Date: December 20, 1983
Creator: Sandoval, R.P.
Partner: UNT Libraries Government Documents Department
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Light water reactor fuel reprocessing: dissolution studies of voloxidized fuel

Description: Voloxidation is a proposed head-end process to remove tritium from irradiated LWR fuel by roasting the fuel in the presence of oxygen. The process oxidizes UO/sub 2/ to a fine U/sub 3/O/sub 8/ powder with high surface area for dissolution. Small-scale tests with irradiated Robinson, Oconee, and Saxton reactor fuels have been made to determine the dissolution behavior of both voloxidized and nonvoloxidized (UO/sub 2/) fuel. No significant technical problems were encountered in batch-dissolving o… more
Date: January 1, 1977
Creator: Johnson, D. R. & Stone, J. A.
Partner: UNT Libraries Government Documents Department
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Treatment of high-level wastes from the IFR fuel cycle

Description: The Integral Fast Reactor (IFR) is being developed as a future commercial power source that promises to have important advantages over present reactors, including improved resource conservation and waste management. The spent metal alloy fuels from an IFR will be processed in an electrochemical cell operating at 500{degree}C with a molten chloride salt electrolyte and cadmium metal anode. After the actinides have been recovered from several batches of core and blanket fuels, the salt cadmium in… more
Date: January 1, 1992
Creator: Johnson, T. R.; Lewis, M. A.; Newman, A. E. & Laidler, J. J.
Partner: UNT Libraries Government Documents Department
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Use of transportable storage casks in the nuclear waste management system: Appendices

Description: A study was performed to determine the viability of the use of transportable storage casks (TSCs), and other metal casks that are designed primarily for storage but which might be used to ship their stored contents to DOE on a one-time use basis (referred to in this study as storage only casks, or SOCs), in the combined utility/DOE spent fuel management system. The viability of the use of TSCs and SOCs was assessed in terms of the costs and savings involved in their use, the sensitivity of thes… more
Date: December 1, 1987
Partner: UNT Libraries Government Documents Department
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Voloxidation studies with UO/sub 2/ reactor fuels

Description: Voloxidation was studied experimentally in small-scale laboratory tests with irradiated UO/sub 2/ reactor fuels. The present study developed new data on the effects on the voloxidation reaction of hull length, oxygen concentration, temperature, agitation, fuel density, and fuel type and burnup. The reaction was studied by measuring weight gains, yields of U/sub 3/O/sub 8/, product densities and particle-size distributions, reaction rates, tritium release, and behavior of other off-gases (/sup 1… more
Date: January 1, 1980
Creator: Stone, J A
Partner: UNT Libraries Government Documents Department
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Consolidated fuel-reprocessing program. Progress report, April 1-June 30, 1982

Description: Highlights of progress accomplished during the quarter ending June 30, 1982 are summarized. Discussion is presented under the headings: Process development; Laboratory R and D; Engineering research; Engineering systems; Integrated equipment test facility operation; Instrument development; and HTGR fuel reprocessing.
Date: September 1, 1982
Creator: Burch, W D
Partner: UNT Libraries Government Documents Department
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Public acceptability of the use of gamma rays from spent nuclear fuel as a hazardous waste treatment process

Description: Three methods were used to estimate public reaction to the use of gamma irradiation of hazardous wastes as a hazardous waste treatment process. The gamma source of interest is spent nuclear fuel. The first method is Benefit-Risk Decision Making, where the benefits of the proposed technology are compared to its risks. The second analysis compares the proposed technology to the other, currently used nuclear technologies and estimates public reaction based on that comparison. The third analysis is… more
Date: January 1, 1992
Creator: Mincher, B. J.; Wells, R. P. & Reilly, H. J.
Partner: UNT Libraries Government Documents Department
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