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Fuel performance annual report for 1989

Description: This annual report, the twelfth in a series, provides a brief description of fuel performance during 1989 in commercial nuclear power plants and an indication of trends. Brief summaries of fuel design changes, fuel surveillance programs, fuel operating experience, fuel problems, high-burnup fuel experience, and items of general significance are provided. References to more detailed information and related US Nuclear Regulatory Commission evaluations are included.
Date: June 1, 1992
Creator: Bailey, W.J.; Berting, F.M. (Pacific Northwest Lab., Richland, WA (United States)) & Wu, S. (Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Characterization of solids in the Three Mile Island Unit 2 Reactor defueling water: Addendum

Description: Shortly after ORNL/TM-10362 was issued, it was discovered that a series of 31 figures had been inadvertently omitted. These figures, which consist of scanning electron microscope (SEM) photographs and energy-dispersive X-ray fluorescence scans, provide significant information about the results obtained in the tests performed with water sample W3. This Addendum includes these figures. Details of and comments on the SEM photographs may be found in ORNL/TM-10362.
Date: March 1, 1988
Creator: Campbell, D.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Structural materials for breeder reactor cores and coolant circuits

Description: The structural components of principal interest in LMFBR cores and cooling circuits include the reactor vessel, primary and secondary piping, intermediate heat exchanger (IHX), and steam generator. Load-bearing components inside the vessel, among these the fuel cladding and duct, are also included. The operating conditions present in a fast-breeder nuclear reactor impose a number of requirements on the mechanical, physical, and neutronic properties of the materials used to construct these compo… more
Date: February 1, 1984
Creator: Diercks, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Once-through steam generator (OTSG) materials and water chemistry. [PWR]

Description: Materials and water chemistry research results associated with the development of the Oconee-1 Reactor steam generator are presented. A summary of water chemistry data acquired during preoperational testing and power operation to date is also included. These data confirm the operational practicality of the nuclear once-through concept using volatile water treatment and high purity condensate demineralized feedwater.
Date: January 1, 1974
Creator: Pocock, F.J. & Levstek, D.F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Background radiation from fission pulses

Description: Extensive source terms for beta, gamma, and neutrons following fission pulses are presented in various tabular and graphical forms. Neutron results from a wide range of fissioning nuclides (42) are examined and detailed information is provided for four fuels: /sup 235/U, /sup 238/U, /sup 232/Th, and /sup 239/Pu; these bracket the range of the delayed spectra. Results at several cooling (decay) times are presented. For ..beta../sup -/ and ..gamma.. spectra, only /sup 235/U and /sup 239/Pu result… more
Date: May 1, 1988
Creator: England, T. R.; Arthur, E. D.; Brady, M. C. & LaBauve, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metals and Ceramics Division. Annual progress report, ending June 30, 1980

Description: Research is reported concerning: (1) engineering materials, including materials compatibility, mechanical properties, nondestructive testing, pressure vessel technology, and welding and brazing; (2) fuels and processes consisting of ceramic technology, fuel cycle technology, fuels evaluation, fuel fabrication and metals processing; and (3) materials science which includes, ceramic studies, physical metallurgy properties, radiation effects and microstructural analysis, metastable and superconduc… more
Date: September 1, 1980
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Passive safety and the advanced liquid metal reactors

Description: Advanced Liquid Metal Reactors being developed today in the USA are designed to make maximum use of passive safety features. Much of the LMR safety work at Argonne National Laboratory is concerned with demonstrating, both theoretically and experimentally, the effectiveness of the passive safety features. The characteristics that contribute to passive safety are discussed, with particular emphasis on decay heat removal systems, together with examples of Argonne's theoretical and experimental pro… more
Date: January 1, 1988
Creator: Hill, D.J.; Pedersen, D.R. & Marchaterre, J.F.
Item Type: Refine your search to only Article
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Methods and techniques of NDA (nondestructive assay)

Description: Nondestructive assay (NDA) refers to techniques and instruments developed to measure nuclear materials in the many forms in which they occur throughout the fuel cycle. These techniques were first developed to support nuclear safeguards inspections and nuclear material accountability; they are also used extensively for process and quality control. Most accountability measurements are based on analytical chemistry and require that a sample be drawn and analyzed destructively. Destructive analysis… more
Date: January 1, 1988
Creator: Reilly, T. D.
Item Type: Refine your search to only Article
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))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nuclear fuel cycle facility accident analysis handbook

Description: The Accident Analysis Handbook (AAH) covers four generic facilities: fuel manufacturing, fuel reprocessing, waste storage/solidification, and spent fuel storage; and six accident types: fire, explosion, tornado, criticality, spill, and equipment failure. These are the accident types considered to make major contributions to the radiological risk from accidents in nuclear fuel cycle facility operations. The AAH will enable the user to calculate source term releases from accident scenarios manual… more
Date: unknown
Creator: Ayer, J. E.; Clark, A. T.; Loysen, P.; Ballinger, M. Y.; Mishima, J.; Owczarski, P. C. et al.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

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
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Some Scoping Experiments for a Space Reactor

Description: Some scoping experiments were performed to evaluate fuel performance in a lithium heat pipe reactor operating at a nominal 1500K heat pipe temperature. Fuel-coolant and fuel-coolant-clad relationships showed that once a failed heat pipe occurs temperatures can rise high enough so that large concentrations of uranium can be transported by the vapor phase. Upon condensation this uranium would be capable of penetrating heat pipes adjacent to the failed pipe. The potential for propagation of failur… more
Date: July 7, 1983
Creator: Alexander, C. A. & Ogden, J. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium compatibility of HT-9 and Fe-9Cr-1Mo steels

Description: Ferritic steels have been receiving significant attention for possible use as steam generator tubing, and as alternate structural materials for liquid-metal heat-transport systems in commercial fast reactors, fusion reactors, etc. The materials are chosen on the basis of their high thermal conductivity, resistance to stress-corrosion-cracking in aqueous and steam environments, favorable fabricability and fairly low cost. These steels are available in several classes based on the microstructure … more
Date: November 1, 1985
Creator: Anantatmula, R. P. & Brehm, W. F.
Item Type: Refine your search to only Article
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Alternative energy sources for non-highway transportation. Appendices

Description: A planning study was made for DOE on alternate fuels for non-highway transportation (aircraft, rail, marine, and pipeline). The study provides DOE with a recommendation of what alternate fuels may be of interest to non-highway transportation users from now through 2025 and recommends R and D needed to allow non-petroleum derived fuels to be used in non-highway transportation. Volume III contains all of the references for the data used in the preliminary screening and is presented in 4 subvolume… more
Date: June 1, 1980
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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