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open access

UPDATE: nuclear power program information and data, July-September 1981

Description: UPDATE is published by the Office of Coordination and Special Projects, Office of Nuclear Reactor Programs, to provide a quick reference source on the current status of nuclear powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses prese… more
Date: January 1, 1981
Creator: /NBM--6011986, DOE
Partner: UNT Libraries Government Documents Department
open access

Scaled Experimental Modeling of VHTR Plenum Flows

Description: Abstract The Very High Temperature Reactor (VHTR) is the leading candidate for the Next Generation Nuclear Power (NGNP) Project in the U.S. which has the goal of demonstrating the production of emissions free electricity and hydrogen by 2015. Various scaled heated gas and water flow facilities were investigated for modeling VHTR upper and lower plenum flows during the decay heat portion of a pressurized conduction-cooldown scenario and for modeling thermal mixing and stratification (“thermal st… more
Date: April 1, 2007
Creator: 15, ICONE
Partner: UNT Libraries Government Documents Department
open access

Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office

Description: Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).
Date: April 1, 1958
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Partner: UNT Libraries Government Documents Department
open access

Feasibility Study, Optimum Partially Enriched Uranium, Gas Cooled, Graphite Moderated for United States Atomic Energy Commission, Idaho Operations Office

Description: Report that contains "a preliminary design and feasibility studies of gas cooled, graphite moderated, nuclear power plants" (p. 1).
Date: April 1, 1958
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Partner: UNT Libraries Government Documents Department
open access

Savannah River Project Site Report: 30,000 KW Prototype Partically Enriched Uranium Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission Idaho Operations Office

Description: Report describing a modified prototype of a nuclear reactor that uses partially uranium-enriched fuel and is cooled by helium. The construction site, site safety aspects, and design and construction costs are included.
Date: March 1959
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Partner: UNT Libraries Government Documents Department
open access

Dose commitments due to radioactive releases from nuclear power plant sites in 1992. Volume 14

Description: Population and individual radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1992. Fifty-year dose commitments for a 1-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teenager, and adult) residing between 2 and 80 km from each of 72 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and… more
Date: March 1, 1996
Creator: Aaberg, R. L. & Baker, D. A.
Partner: UNT Libraries Government Documents Department
open access

Management of intermediate-level radioactive wastes in the United States

Description: While used extensively, the term intermediate-level waste is not a clearly defined waste category. Assuming the ILW includes all radioactive wastes requiring shielding but not ordinarily included in a high-level waste canister, its major sources include power plant operations, spent fuel storage, and spent fuel reprocessing. While the volume is approx. 10/sup 2/ greater than that of high-level waste, ILW contains only approx. 1% of the radioactivity. Power plant waste, constituting approx. 87% … more
Date: July 1, 1980
Creator: Aaberg, R.L.; Lakey, L.T. & Greenborg, J.
Partner: UNT Libraries Government Documents Department
open access

Water-related planning and design at energy firms

Description: Water related planning and design at energy firms are examined. By identifying production alternatives and specifying the cost of these alternatives under a variety of conditions, one gains insight into the future pattern of water use in the energy industry and the response of industry to water-related regulation. In Part II, the three principal decisions of industry that affect water allocation are reviewed: where to build plants, where to get water, and how much water to use. The cost of wate… more
Date: November 1, 1980
Creator: Abbey, D & Lucero, F
Partner: UNT Libraries Government Documents Department
open access

Interim assessment of the denatured /sup 233/U fuel cycle: feasibility and nonproliferation characteristics

Description: A fuel cycle that employs /sup 233/U denatured with /sup 238/U and mixed with thorium fertile material is examined with respect to its proliferation-resistance characteristics and its technical and economic feasibility. The rationale for considering the denatured /sup 233/U fuel cycle is presented, and the impact of the denatured fuel on the performance of Light-Water Reactors, Spectral-Shift-Controlled Reactors, Gas-Cooled Reactors, Heavy-Water Reactors, and Fast Breeder Reactors is discussed.… more
Date: December 1, 1979
Creator: Abbott, L.S.; Bartine, D.E. & Burns, T.J. (eds.)
Partner: UNT Libraries Government Documents Department
open access

Interim assessment of the denatured /sup 233/U fuel cycle: feasibility and nonproliferation characteristics

Description: A fuel cycle that employs /sup 233/U denatured with /sup 238/U and mixed with thorium fertile material is examined with respect to its proliferation-resistance characteristics and its technical and economic feasibility. The rationale for considering the denatured /sup 233/U fuel cycle is presented, and the impact of the denatured fuel on the performance of Light-Water Reactors, Spectral-Shift-Controlled Reactors, Gas-Cooled Reactors, Heavy-Water Reactors, and Fast Breeder Reactors is discussed.… more
Date: December 1, 1978
Creator: Abbott, L.S.; Bartine, D.E. & Burns, T.J. (eds.)
Partner: UNT Libraries Government Documents Department
open access

Radionuclide characterization at US commercial light-water reactors for decommissioning assessment: Distributions, inventories, and waste disposal considerations

Description: A continuing research program, conducted by Pacific Northwest Laboratory for the US Nuclear Regulatory Commission, characterizing radionuclide concentrations associated with US light-water reactors has been conducted for more than a decade. The research initially focused upon sampling and analytical measurements for the purpose of establishing radionuclide distributions and inventories for decommissioning assessment, since very little empirical data existed. The initial phase of the research pr… more
Date: September 1, 1992
Creator: Abel, K. H.; Robertson, D. E. & Thomas, C. W.
Partner: UNT Libraries Government Documents Department
open access

Radionuclide characterization at US commercial light-water reactors for decommissioning assessment: Distributions, inventories, and waste disposal considerations

Description: A continuing research program, conducted by Pacific Northwest Laboratory for the US Nuclear Regulatory Commission, characterizing radionuclide concentrations associated with US light-water reactors has been conducted for more than a decade. The research initially focused upon sampling and analytical measurements for the purpose of establishing radionuclide distributions and inventories for decommissioning assessment, since very little empirical data existed. The initial phase of the research pr… more
Date: September 1, 1992
Creator: Abel, K. H.; Robertson, D. E. & Thomas, C. W.
Partner: UNT Libraries Government Documents Department
open access

Health effects models for nuclear power plant accident consequence analysis. Modification of models resulting from addition of effects of exposure to alpha-emitting radionuclides: Revision 1, Part 2, Scientific bases for health effects models, Addendum 2

Description: The Nuclear Regulatory Commission (NRC) has sponsored several studies to identify and quantify, through the use of models, the potential health effects of accidental releases of radionuclides from nuclear power plants. The Reactor Safety Study provided the basis for most of the earlier estimates related to these health effects. Subsequent efforts by NRC-supported groups resulted in improved health effects models that were published in the report entitled {open_quotes}Health Effects Models for N… more
Date: May 1, 1993
Creator: Abrahamson, S.; Bender, M. A.; Boecker, B. B.; Scott, B. R. & Gilbert, E. S.
Partner: UNT Libraries Government Documents Department
open access

Health effects models for nuclear power plant accident consequence analysis: Modifications of models resulting from recent reports on health effects of ionizing radiation

Description: The Nuclear Regulatory Commission has sponsored several studies to identify and quantify the potential health effects of accidental releases of radionuclides from nuclear power plants. The most recent health effects models resulting from these efforts were published in two reports, NUREG/CR-4214, Rev. 1, Part 1 (1990) and Part 2 (1989). Several major health effects reports have been published recently that may impact the health effects models presented in these reports. This addendum to the Par… more
Date: August 1, 1991
Creator: Abrahamson, S.; Bender, M. A.; Boecker, B. B.; Scott, B. R. & Gilbert, E. S.
Partner: UNT Libraries Government Documents Department
open access

Health effects models for nuclear power plant accident consequence analysis: Low LET radiation: Part 2, Scientific bases for health effects models

Description: This report provides dose-response models intended to be used in estimating the radiological health effects of nuclear power plant accidents. Models of early and continuing effects, cancers and thyroid nodules, and genetic effects are provided. Two-parameter Weibull hazard functions are recommended for estimating the risks of early and continuing health effects. Three potentially lethal early effects -- the hematopoietic, pulmonary and gastrointestinal syndromes -- are considered. Linear and li… more
Date: May 1, 1989
Creator: Abrahamson, S.; Bender, M.; Book, S.; Buncher, C.; Denniston, C.; Gilbert, E. et al.
Partner: UNT Libraries Government Documents Department
open access

International nuclear waste management fact book

Description: The International Nuclear Waste Management Fact Book has been compiled to provide current data on fuel cycle and waste management facilities, R and D programs, and key personnel in 24 countries, including the US; four multinational agencies; and 20 nuclear societies. This document, which is in its second year of publication supersedes the previously issued International Nuclear Fuel Cycle Fact Book (PNL-3594), which appeared annually for 12 years. The content has been updated to reflect current… more
Date: November 1995
Creator: Abrahms, C. W.; Patridge, M. D. & Widrig, J. E.
Partner: UNT Libraries Government Documents Department
open access

Fission product plateout/liftoff/washoff test plan. Revision 1

Description: A test program is planned in the COMEDIE loop of the Commissariat a l`Energy Atomique (CEA), Grenoble, France, to generate integral test data for the validation of computer codes used to predict fission product transport and core corrosion in the Modular High Temperature Gas-Cooled Reactor (MHTGR). The inpile testing will be performed by the CEA under contract from the US Department of Energy (DOE); the contract will be administered by Oak Ridge National Laboratory (ORNL). The primary purpose o… more
Date: May 1, 1988
Creator: Acharya, R. & Hanson, D.
Partner: UNT Libraries Government Documents Department
open access

An investigation of temperature measurement methods in nuclear power plant reactor pressure vessel annealing

Description: The objective of this project was to provide an assessment of several methods by which the temperature of a commercial nuclear power plant reactor pressure vessel (RPV) could be measured during an annealing process. This project was a coordinated effort between DOE`s Office of Nuclear Energy, Science and Technology; DOE`s Light Water Reactor Technology Center at Sandia National Laboratories; and the Electric Power Research Institute`s Non- Destructive Evaluation Center. Ball- thermocouple probe… more
Date: May 1996
Creator: Acton, R.U.; Gill, W.; Sais, D.J.; Schulze, D.H. & Nakos, J.T.
Partner: UNT Libraries Government Documents Department
open access

Operating procedure for SiC defect detection: Data support document

Description: The feasibility of the Hg Intrusion QC method for measuring SiC coating defects for the MHTGR was conducted as a potential improvement for the Burn/Leach (B/L) QC method currently used. The purpose for evaluating the Hg Intrusion QC method as an alternative method was to determine if B/L QC method underestimated SiC coating defects. Some evidence in work conducted earlier, indicated that TRISO-coated fuel particles with low SiC coating defects measured by the B/L QC method showed higher release… more
Date: September 29, 1989
Creator: Adams, C. C. & Partain, K. E.
Partner: UNT Libraries Government Documents Department
open access

Defect fractions for fissile and fertile TRISO-coated fuel

Description: High quality TRISCO-coated UCO and ThO{sub 2} particles with reference MHTGR dimensions were produced in a coating campaign in August and September 1986 for irradiation tests. The heavy metal contamination and the defect levels were below the limits established for the MHTGR fuel. Over 9 kg of uranium in UCO and 30 kg of thorium in ThO{sub 2} were TRISCO-coated in 4 fissile and 3 fertile batches in the 240mm Development Coater. These coated fuel particles will be used to produce fuel rods for t… more
Date: September 1, 1986
Creator: Adams, C.C.
Partner: UNT Libraries Government Documents Department
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Development of improved TRISO-P fuel particle P-PyC coating

Description: Low defect fuels are required for the MHTGR to meet tighter fuel performance for this reactor design (Ref. 1). Exposed heavy metal (HM) contamination levels must be reduced to {le} 1E-5 fraction. Particle coating breakage during the fuel compact fabrication process has been shown to be a major source of HM contamination in the final fuel compacts. Excessive forces are experienced by the coated fuel particles during matrix injection, which leads to coating failure. Adding a sacrificial, low Youn… more
Date: April 29, 1988
Creator: Adams, C.C.
Partner: UNT Libraries Government Documents Department
open access

Critical evaluation of the nonradiological environmental technical specifications. Program description, summary, and recommendations. Vol. 1

Description: A comprehensive study of the data collected as part of the environmental Technical Specifications program for eight nuclear power plants was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory commission. This report includes a summary of the screening phase in which the adequacy of the hydrothermal and ecological monitoring data for each plant were evaluated, and the summary and recommendations resulting from a detailed examination of the three nuclear power … more
Date: August 10, 1976
Creator: Adams, S. M.; Cunningham, P. A.; Gray, D. D.; Kumar, K. D. & Witten, A. J.
Partner: UNT Libraries Government Documents Department
open access

Methodologies for assessment of power plant ecological effects in the marine environment

Description: Various types of models or methodologies relevant to the assessment of entrainment, thermal, and impingement impacts of power plant operation in the marine environment are presented. The majority of methodologies available for assessing power plant effects are focused at the organism or population level. The most widely applied approaches for estimating entrainment effects on fish populations are the equivalent adult and trophic-conversion methodologies. Current methods to predict the number of… more
Date: January 1, 1978
Creator: Adams, S.M.
Partner: UNT Libraries Government Documents Department
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