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Technology, Safety and Costs of Decommissioning a Reference Uranium Hexafluoride Conversion Plant

Description: Safety and cost information is developed for the conceptual decommissioning of a commercial uranium hexafluoride conversion (UF{sub 6}) plant. Two basic decommissioning alternatives are studied to obtain comparisons between cost and safety impacts: DECON, and passive SAFSTOR. A third alternative, DECON of the plant and equipment with stabilization and long-term care of lagoon wastes. is also examined. DECON includes the immediate removal (following plant shutdown) of all radioactivity in excess… more
Date: October 1, 1981
Creator: Elder, H. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aerosols Generated by Free Fall Spills of Powders and Solutions in Static Air

Description: Safety assessments and environmental impact statements for nuclear fuel cycle facilities require an estimation of potential airborne releases. Aerosols generated by accidents are being investigated to develop the source terms for these releases. The lower boundary accidental release event would be a free fall spill of powders or liquids in static air. Experiments measured the mass airborne and particle size distribution of these aerosols for various source sizes and spill heights. Two powder an… more
Date: December 1, 1981
Creator: Sutter, S. L.; Johnston, J. W. & Mishima, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SULFUR HEXAFLUORIDE TREATMENT OF USED NUCLEAR FUEL TO ENHANCE SEPARATIONS

Description: Reactive Gas Recycling (RGR) technology development has been initiated at Savannah River National Laboratory (SRNL), with a stretch-goal to develop a fully dry recycling technology for Used Nuclear Fuel (UNF). This approach is attractive due to the potential of targeted gas-phase treatment steps to reduce footprint and secondary waste volumes associated with separations relying primarily on traditional technologies, so long as the fluorinators employed in the reaction are recycled for use in th… more
Date: September 25, 2012
Creator: Gray, J.; Torres, R.; Korinko, P.; Martinez-Rodriguez, M.; Becnel, J.; Garcia-Diaz, B. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Accident Generated Particulate Materials and Their Characteristics -- A Review of Background Information

Description: Safety assessments and environmental impact statements for nuclear fuel cycle facilities require an estimate of the amount of radioactive particulate material initially airborne (source term) during accidents. Pacific Northwest Laboratory (PNL) has surveyed the literature, gathering information on the amount and size of these particles that has been developed from limited experimental work, measurements made from operational accidents, and known aerosol behavior. Information useful for calculat… more
Date: May 1, 1982
Creator: Sutter, S. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radon Diffusion Through Uranium Mill Tailings and Cover Defects

Description: Research was conducted at Pacific Northwest Laboratory to define the effects of cover defects on the emission of radon gas from covered uranium mill tailings piles. This report describes the results from the analysis of four geometrically simplified cover defects.
Date: December 1, 1981
Creator: Mayer, D. W. & Zimmerman, D. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Review of Design Approaches Applicable to Dewatering Uranium Mill Tailings Disposal Pits

Description: This report is a review of design approaches in the literature that may be applicable to uranium mill tailings drainage. Tailings dewatering is required in the deep mined-out pits used for wet tailings disposal. Agricultural drainage theory is reviewed because it is seen as the most applicable technology. It is concluded that the standard drain-pipe envelope design criteria should be easily adapted. The differences in dewatering objectives and physical characteristics between agricultural and t… more
Date: March 1, 1982
Creator: Gutknecht, P. J. & Gates, T. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Environmental Assessment Methodology for the Nuclear Fuel Cycle

Description: This report describes the methodology for determining where environmental control technology is required for the nuclear fuel cycle. The methodology addresses routine emission of chemical and radioactive effluents, and applies to mining, milling, conversion, enrichment, fuel fabrication, reactors (LWR and BWR) and fuel reprocessing. Chemical and radioactive effluents are evaluated independently. Radioactive effluents are evaluated on the basis of maximum exposed individual dose and population d… more
Date: July 1, 1977
Creator: Brenchley, D. L.; Soldat, J. K.; McNeese, J. A. & Watson, E. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Criticality Experiments with Mixed Plutonium and Uranium Nitrate Solution at a Plutonium Fraction of 0.5 in Annular Cylindrical Geometry

Description: A series of critical experiments was completed with mixed plutonium-uranium solutions having Pu/(Pu + U) ratios of approximately 0.5. These experiments were a 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, and data from, the experiments are included in this report. The experiments were performed with mixed plutonium-uranium solutions… more
Date: April 1, 1988
Creator: Lloyd, RC
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SAVANNAH RIVER SITE'S H-CANYON FACILITY: RECOVERY AND DOWN BLEND URANIUM FOR BENEFICIAL USE

Description: For over fifty years, the H Canyon facility at the Savannah River Site (SRS) has performed remotely operated radiochemical separations of irradiated targets to produce materials for national defense. Although the materials production mission has ended, the facility continues to play an important role in the stabilization and safe disposition of proliferable nuclear materials. As part of the US HEU Disposition Program, SRS has been down blending off-specification (off-spec) HEU to produce LEU si… more
Date: May 27, 2013
Creator: Magoulas, V.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Criticality Experiments with Subcritical Clusters of 2.35 Wt% and 4.31 Wt% 235U Enriched U02 Rods in Water with Uranium or Lead Reflecting Walls Undermoderated Water-to-Fuel Volume Ratio of 1.6

Description: A series of criticality experiments with undermoderated (1.6 water-to-fuel volume ratio) 2.35 wt% and 4.31 wt% {sup 235}U enriched UO{sub 2} rods in water were performed to provide data on the reactivity effects of lead and depleted uranium reflecting walls. This data furnishes well defined benchmarks for use in validating calculational techniques employed in analyzing fuel shipping and storage systems having lead or uranium biological shields. For each fuel enrichment, the critical separation … more
Date: December 1, 1981
Creator: Bierman, S. R.; Durst, B. M. & Clayton, E. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical Support for Improving the Licensing Regulatory Base for Selected Facilities Associated with the Front End of the Fuel Cycle

Description: Pacific Northwest Laboratory (PNL) was asked by the NRC Office of Nuclear Material Safety and Safeguards (NMSS) to determine the adequacy of its health, safety and environmental regulatory base as a guide to applicants for licenses to operate UF{sub 6} conversion facilities and fuel fabrication plants. The regulatory base was defined as the body of documented requirements and guidance to licensees, including laws passed by Congress, Federal Regulations developed by the NRC to implement the laws… more
Date: April 1, 1982
Creator: Clark, R. G.; Schreiber, R. E.; Jamison, J. D.; Davenport, L. C. & Brite, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Criticality Experiments with Mixed Plutonium and Uranium Nitrate Solution at a Plutonium Fraction of 0.2 and 1.0 in Annular Cylindrical Geometry

Description: A series of critical experiments was completed with mixed plutoniumuranium solutions having Pu/(Pu + U) ratios of approximately 0.2 and 1.0. These experiments were a 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, and data from, the experiments are included in this report. The experiments were performed with mixed plutonium-uranium so… more
Date: April 1, 1988
Creator: Lloyd, RC
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cryogenic Thermal Expansion of Y-12 Graphite Fuel Elements

Description: Thermal expansion measurements betwccn 20°K and 300°K were made on segments of three uranium-loaded Y-12 uncoated graphite fuel elements. The thermal expansion of these fuel elements over this temperature range is represented by the equation: {Delta}L/L = -39.42 x 10{sup -5} + 1.10 x 10{sup -7} T + 6.47 x 10{sup -9} T{sup 2} - 8.30 x 10{sup -12} T{sup 3}.
Date: July 8, 2013
Creator: Eash, D. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radkowsky Thorium Fuel Project

Description: In the early/mid 1990’s Prof. Alvin Radkowsky, former chief scientist of the U.S. Naval Reactors program, proposed an alternate fuel concept employing thorium-based fuel for use in existing/next generation pressurized water reactors (PWRs). The concept was based on the use of a 'seed-blanket-unit' (SBU) that was a one-for-one replacement for a standard PWR assembly with a uranium-based central 'driver' zone, surrounded by a 'blanket' zone containing uranium and thorium. Therefore, the SBU could… more
Date: December 31, 2006
Creator: Todosow, Michael
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Compatibility of uranium-plutonium carbide fuels and potential LMFBR cladding materials

Description: The contact compatibility (in the absence of sodium) between (U,Pu)C with equivalent carbon contents of 4.83, 5.25, and 6.75 wt % and iron-, nickel- and vanadium-base alloys was studied at 700-1100{deg}C for 168-4000 hr. Austenitic iron-base alloys, containing 25 wt % or less nickel and tested at 800{deg}C for up to 4000 hr, showed little or no evidence of carbon transfer from stoichiometric or hyperstoichiometric (U{sub 0.8}Pu{sub 0.2})C that contained up to 20 vol % (U,Pu){sub 2}C{sub 3}. Thr… more
Date: September 1, 1971
Creator: Latimer, T W
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FUEL PERFORMANCE IMPROVEMENT PROGRAM - Quarterly Progress Report April - June 1978 FUEL PERFORMANCE IM?ROVEMENT PROGRAM FUEL PERFORMANCE PROGRAM: Quarterly Progress Report April June 1978

Description: The objectives of the Fuel Performance Improvement Program (FPIP) are to identify and demonstrate fuel concepts with improved performance and to provide the supportive technical bases for developing commercial fuel designs that are capable of achieving hiqh burnup for better utilization of uranium.
Date: July 1, 1978
Creator: Crouthamel, CE
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Criticality Experiments with Subcritical Clusters of 2.35 Wt% and 4.31 Wt% {sup 235}U Enriched UO{sub 2} Rods in Water with Steel Reflecting Walls

Description: A series of criticality experiments with 2.35 wt% and 4.31 wt% {sup 235}U enriched UO{sub 2} rods in water were performed to provide well defined benchmark type data on the effects of thick steel reflecting walls. For each fuel enrichment. the critical separation between three subcritical fuel clusters was observed to increase as 178.5 mm thick reflecting walls of reactor grade steel was moved towards the fuel. This increase was observed for fuel clusters having an undermoderated water-to-fuel … more
Date: April 1, 1981
Creator: Bierman, S. R. & Clayton, E. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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RESEARCH AND DEVELOPMENT ACTIVITIES AT SAVANNAH RIVER SITE'S H CANYON FACILITY

Description: The Savannah River Site's (SRS) H Canyon Facility is the only large scale, heavily shielded, nuclear chemical separations plant still in operation in the U.S. The facility's operations historically recovered uranium-235 (U-235) and neptunium-237 (Np-237) from aluminum-clad, enriched-uranium fuel tubes from Site nuclear reactors and other domestic and foreign research reactors. Today the facility, in conjunction with HB Line, is working to provide the initial feed material to the Mixed… more
Date: July 9, 2013
Creator: Sexton, L. & Fuller, Kenneth
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Solubility Classification of Airborne Uranium Products from LWR-Fuel Plants

Description: Airborne dust samples were obtained from various locations within plants manufacturing fuel elements for light-water reactors, and the dissolution rates of uranium from these samples into simulated lung fluid at 37°C were measured. These measurements were used to classify the solubilities of the samples in terms of the lung clearance model proposed by the International Commission on Radiological Protection. Similar evaluations were performed for samples of pure uranium compounds expected as com… more
Date: August 1, 1980
Creator: kalkwarf, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fundamental Studies of Irradiation-Induced Defect Formation and Fission Product Dynamics in Oxide Fuels

Description: The objective of this research program is to address major nuclear fuels performance issues for the design and use of oxide-type fuels in the current and advanced nuclear reactor applications. Fuel performance is a major issue for extending fuel burn-up which has the added advantage of reducing the used fuel waste stream. It will also be a significant issue with respect to developing advanced fuel cycle processes where it may be possible to incorporate minor actinides in various fuel forms so t… more
Date: December 19, 2012
Creator: Stubbins, James
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactivity Initiated Accident Test Series RIA Scoping Test Experiment Predictions

Description: The Reactivity 'Initiated Accident (RIA) test series to be conducted in the Power Burst Facility (PBF) has been designed.to determine fuel failure thresholds, modes, and consequences as a function of energy deposition, irradiation history, and fuel design. The RIA Scoping Test will be comprised of five single unirradiated rod sub-tests. The first rod will be subjected to a series of transient power bursts of increasing energy release to determine the energy deposition at cladding failure. … more
Date: June 1978
Creator: Semken, R. S.; Eaton, A. M.; Smith, R. H. & Resch, S. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Outline for Book: Engineering for Nuclear Reactor Fuel Reprocessing

Description: This document outlines a book on the subject of reactor fuel reprocessing that is still in the planning stages, representing the authors' thinking as of the arbitrary cut-off date of October 15, 1957. The subject matter that was intended for inclusion was: special considerations in radiochemical processing; chemical processes and operations; mechanical operations; fluid flow; heat transfer operations; solvent extraction; other mass diffusion operations; instrumentation; auxiliary equipment… more
Date: November 15, 1957
Creator: Long, J. T.; Carter, W. L. & Rom, A. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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