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Reviews of ASME Section 11 pump and valve relief requests: Post Generic Letter 89-04

Description: This paper presents a discussion of ASME Section 11 Pump and Valve Inservice Testing relief request reviews by the NRC and their contractors. Topics that will be discussed include the scope of USNRC reviews in Technical Evaluation Reports (TERs) (and Safety Evaluation, SEs); including the basis for granting relief requests, the status of relief requests in IST Program updates, and the Generic Letter 89-04 approval process; and the level of technical detail required in submitted programs. This p… more
Date: January 1, 1992
Creator: DiBiasio, A.
Partner: UNT Libraries Government Documents Department
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Department of Energy Nuclear Energy Standards Program

Description: The policy with respect to the development and use of standards in the Department of Energy (DOE) programs concerned with maintaining and developing the nuclear option for the civilian sector (both in the form of the currently used light water reactors and for advanced concepts including the Liquid Metal Fast Breeder Reactor), is embodied in a Nuclear Standards Policy, issued in 1978, whose perspectives and philosophy are discussed.
Date: January 1, 1980
Creator: Silver, E.G.
Partner: UNT Libraries Government Documents Department
open access

Nuclear facility licensing, documentaion, and reviews, and the SP-100 test site experience

Description: The required approvals and permits to test a nuclear facility are extensive. Numerous regulatory requirements result in the preparation of documentation to support the approval process. The principal regulations for the SP-100 Ground Engineering System (GES) include the National Environmental Policy Act, Clean Air Act, and Atomic Energy Act. The documentation prepared for the SP-100 Nuclear Assembly Test (NAT) included an Environmental Assessment, state permit applications, and Safety Analysis … more
Date: June 1, 1991
Creator: Cornwell, B. C.; Deobald, T. L. & Bitten, E. J.
Partner: UNT Libraries Government Documents Department
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Financial and ratepayer impacts of nuclear power plant regulatory reform

Description: Three reports - ''The Future Market for Electric Generating Capacity,'' ''Quantitative Analysis of Nuclear Power Plant Licensing Reform,'' and ''Nuclear Rate Increase Study'' are recent studies performed by the Los Alamos National Laboratory that deal with nuclear power. This presents a short summary of these three studies. More detail is given in the reports.
Date: January 1, 1985
Creator: Turpin, A. G.
Partner: UNT Libraries Government Documents Department
open access

Licensing of away-from-reactor (AFR) installations

Description: Storage of spent fuel at Away-From-Reactor (AFR) installations will allow reactors to continue to operate until reprocessing or other fuel disposal means are available. AFR installations must be licensed by the Nuclear Regulatory Commission (NRC). Although wide experience in licensing reactors exists, the licensing of an AFR installation is a relatively new activity. Only one has been licensed to date. This paper delineates the requirements for licensing an AFR installation and projects a licen… more
Date: January 1, 1980
Creator: Gray, P L
Partner: UNT Libraries Government Documents Department
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Validation of ANS-5. 1 as the decay heat standard at the Savannah River Plant

Description: The Savannah River Laboratory (SRL) is upgrading the methods used to predict the post shutdown decay heat of the Savannah River reactors by implementing procedures based on the ANS Decay Heat Power in Light Water Reactors standard. This approach takes advantage of the large volume of research used in developing the standard and establishes compatibility with the nuclear industry. To qualify the decay heat standard for use, a series of comparisons were made between detailed decay heat calculatio… more
Date: January 1, 1982
Creator: Apperson, Jr, C. E.
Partner: UNT Libraries Government Documents Department
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Comments on regulatory reform

Description: Nuclear regulatory reform is divided into two parts. The first part contains all those matters for which new legislation is required. The second part concerns all those matters that are within the power of the Commission under existing statutes. Recommendations are presented.
Date: January 1, 1982
Creator: Hendrie, J. M.
Partner: UNT Libraries Government Documents Department
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Reduced-size plutonium sample processing and packaging for the PAT-2 package

Description: A light-water container for the air transport of plutonium safeguards samples, the PAT-2 package, has been developed in the USA and is now licensed by the US NRC (Certificate of Compliance) and the US DOT (IAEA Certificate of Competent Authority). The very limited available space in this package for plutonium-bearing samples required the design of small-size canisters to meet the needs of international safeguards. The suitability of a new small canister and vial for powder and solution samples … more
Date: January 1, 1982
Creator: Kuhn, E.; Deron, S.; Aigner, H. & Andersen, J. A.
Partner: UNT Libraries Government Documents Department
open access

Nuclear power plant simulation facility evaluation methodology

Description: A methodology for evaluation of nuclear power plant simulation facilities with regard to their acceptability for use in the US Nuclear Regulatory Commission (NRC) operator licensing exam is described. The evaluation is based primarily on simulator fidelity, but incorporates some aspects of direct operator/trainee performance measurement. The panel presentation and paper discuss data requirements, data collection, data analysis and criteria for conclusions regarding the fidelity evaluation, and … more
Date: January 1, 1985
Creator: Haas, P.M.; Carter, R.J. & Laughery, K.R. Jr.
Partner: UNT Libraries Government Documents Department
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MHTGR (Modular High-Temperature Gas-Cooled Reactor) technology development plan

Description: This paper presents the approach used to define the technology program needed to support design and licensing of a Modular High-Temperature Gas-Cooled Reactor (MHTGR). The MHTGR design depends heavily on data and information developed during the past 25 years to support large HTGR (LHTGR) designs. The technology program focuses on MHTGR-specific operating and accident conditions, and on validation of models and assumptions developed using LHTGR data. The technology program is briefly outlined, … more
Date: January 1, 1988
Creator: Homan, F.J. & Neylan, A.J.
Partner: UNT Libraries Government Documents Department
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Safety aspects of the US advanced LMR (liquid metal reactor) design

Description: The cornerstones of the United States Advanced Liquid Metal Cooled Reactor (ALMR) program sponsored by the Department of Energy are: the plant design program at General Electric based on the PRISM (Power Reactor Innovative Small Module) concept, and the Integral Fast Reactor program (IFR) at Argonne National Laboratory (ANL). The goal of the US program is to produce a standard, commercial ALMR, including the associated fuel cycle. This paper discusses the US regulatory framework for design of a… more
Date: January 1, 1989
Creator: Pedersen, D.R.; Gyorey, G. L.; Marchaterre, J. F.; Rosen, S. (Argonne National Lab., IL (USA); General Electric Co., San Jose, CA (USA); Argonne National Lab., IL (USA) et al.
Partner: UNT Libraries Government Documents Department
open access

Pu/U safeguards samples licensed for the PAT-2

Description: A development program for a Lightweight Air-transportable Accident Resistant Container (LAARC), to be used for the timely transport of plutonium or uranium safeguards samples to International Atomic Energy Agency (IAEA) laboratories, in support of the Non Proliferation Treaty (NPT), has resulted in the availability of the Plutonium Air Transportable Model 2 Package (PAT-2 Package). The PAT-2 can survive a severe aircraft crash and resulting fire, providing a virtually unassailable sealed pressu… more
Date: January 1, 1982
Creator: Andersen, J. A.
Partner: UNT Libraries Government Documents Department
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The NRC/SNL (Nuclear Regulatory Commission)/(Sandia National Laboratory) performance assessment methodology for low-level radioactive waste facilities

Description: A performance assessment methodology has been developed for use by the US Nuclear Regulatory Commission (NRC) in evaluating license applications for low-level waste disposal facilities. This paper provides a summary of the modeling approaches selected for the methodology, and includes discussions of the philosophy and structure of the methodology. The performance assessment methodology is designed to provide the NRC with a tool for performing confirmatory analyses in support of license reviews … more
Date: January 1, 1991
Creator: Kozak, M.W.
Partner: UNT Libraries Government Documents Department
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On reactor type comparisons for the next generation of reactors

Description: In this paper, we present a broad comparison of studies for a selected set of parameters for different nuclear reactor types including the next generation. This serves as an overview of key parameters which provide a semi-quantitative decision basis for selecting nuclear strategies. Out of a number of advanced reactor designs of the LWR type, gas cooled type, and FBR type, currently on the drawing board, the Advanced Light Water Reactors (ALWR) seem to have some edge over other types of the nex… more
Date: August 22, 1991
Creator: Alesso, H.P. & Majumdar, K.C.
Partner: UNT Libraries Government Documents Department
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Modeling and analysis of the unprotected loss-of-flow accident in the Clinch River Breeder Reactor

Description: The influence of fission-gas-driven fuel compaction on the energetics resulting from a loss-of-flow accident was estimated with the aid of the SAS3D accident analysis code. The analysis was carried out as part of the Clinch River Breeder Reactor licensing process. The TREAT tests L6, L7, and R8 were analyzed to assist in the modeling of fuel motion and the effects of plenum fission-gas release on coolant and clad dynamics. Special, conservative modeling was introduced to evaluate the effect of … more
Date: January 1, 1985
Creator: Morris, E. E.; Dunn, F. E.; Simms, R. & Gruber, E. E.
Partner: UNT Libraries Government Documents Department
open access

Risk-Based Plant Performance Indicators

Description: Tasked by the 1979 President's Commission on the Accident at Three Mile Island, the US nuclear power industry has put into place a performance indicator program as one means for showing a demonstrable record of achievement.'' Largely through the efforts of the Institute of Nuclear Power Operations (INPO), plant performance data has, since 1983, been collected and analyzed to aid utility management in measuring their plants' performance progress. The US Nuclear Regulatory Commission (NRC) has al… more
Date: January 1, 1989
Creator: Boccio, J. L.; Azarm, M. A.; Vesely, W. E. & Hall, R. E.
Partner: UNT Libraries Government Documents Department
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Automated sensitivity analysis of the radionuclide migration code UCBNE10. 2

Description: The Salt Repository Project (SRP) of the US Department of Energy is performing ongoing performance assessment analyses for the eventual licensing of an underground high-level nuclear waste repository in salt. As part of these studies, sensitivity and uncertainty analysis play a major role in the identification of important parameters, and in the identification of specific data needs for site characterization. Oak Ridge National Laboratory has supported the SRP in this effort resulting in the de… more
Date: January 1, 1985
Creator: Pin, F. G.; Worley, B. A.; Oblow, E. M.; Wright, R. Q. & Harper, W. V.
Partner: UNT Libraries Government Documents Department
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ANS shielding standards for light-water reactors

Description: The purpose of the American Nuclear Society Standards Subcommittee, ANS-6, Radiation Protection and Shielding, is to develop standards for radiation protection and shield design, to provide shielding information to other standards-writing groups, and to develop standard reference shielding data and test problems. A total of seven published ANS-6 standards are now current. Additional projects of the subcommittee, now composed of nine working groups, include: standard reference data for multigrou… more
Date: January 1, 1982
Creator: Trubey, D. K.
Partner: UNT Libraries Government Documents Department
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Radiation protection and shielding standards for the 1980s

Description: The American Nuclear Society (ANS) is a standards-writing organization member of the American National Standards Institute (ANSI). The ANS Standards Committee has a subcommittee denoted ANS-6, Radiation Protection and Shielding, whose charge is to develop standards for radiation protection and shield design, to provide shielding information to other standards-writing groups, and to develop standard reference shielding data and test problems. This paper is a progress report of this subcommittee.… more
Date: January 1, 1982
Creator: Trubey, D.K.
Partner: UNT Libraries Government Documents Department
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Los Alamos National Laboratory and technology transfer

Description: From its beginning in 1943, Los Alamos National Laboratory (Los Alamos) has traditionally used science and technology to fine creative, but practical solutions to complex problems. Los Alamos National Laboratory is operated by the University of California, under contact to the Department of Energy. We are a Government Owned-contractor Operated (GOCO) facility, and a Federally-funded research and Development Center (FFRDC). At Los Alamos, our mission is to apply science and engineering capabilit… more
Date: January 1, 1992
Creator: Bearce, T.D.
Partner: UNT Libraries Government Documents Department
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Safety and licensing analysis of 471 MWt PRISM reactor module

Description: Independent analyses of unscrammed events postulated for the 471 MW PRISM reactor module, as performed by Brookhaven National Laboratory for the US Nuclear Regulatory Commission, are discussed. Peak fuel, cladding, and sodium temperatures for several postulated events were compared against current temperatures limits. For the postulated unscrammed loss of flow (ULOF) events, the newly added Gas Expansion Modules (GEMs), have improved the passive shutdown response. For the unscrammed transient o… more
Date: January 1, 1991
Creator: Van Tuyle, G.J.; Slovik, G.C. (Brookhaven National Lab., Upton, NY (United States)); Throm, E.D. & Sands, S.P. (Nuclear Regulatory Commission, Washington, DC (United States))
Partner: UNT Libraries Government Documents Department
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Use of process monitoring for verifying facility design of large-scale reprocessing plants

Description: During the decade of the 1990s, the International Atomic Energy Agency (IAEA) faces the challenge of implementing safeguards in large, new reprocessing facilities. The Agency will be involved in the design, construction, checkout and initial operation of these new facilities to ensure effective safeguards are implemented. One aspect of the Agency involvement is in the area of design verification. The United States Support Program has initiated a task to develop methods for applying process data… more
Date: January 1, 1991
Creator: Hakkila, E.A.; Zack, N.R. (Los Alamos National Lab., NM (USA)); Ehinger, M.H. (Oak Ridge National Lab., TN (USA)) & Franssen, F. (International Atomic Energy Agency, Vienna (Austria))
Partner: UNT Libraries Government Documents Department
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Safety aspects of the Modular High-Temperature Gas-Cooled Reactor (MHTGR)

Description: The Modular High-Temperature Gas-Cooled Reactor (MHTGR) is an advanced reactor concept under development through a cooperative program involving the US Government, the nuclear industry and the utilities. The design utilizes the basic high-temperature gas-cooled reactor (HTGR) features of ceramic fuel, helium coolant, and a graphite moderator. The qualitative top-level safety requirement is that the plant's operation not disturb the normal day-to-day activities of the public. The MHTGR safety re… more
Date: August 1, 1989
Creator: Silady, F.A. & Millunzi, A.C.
Partner: UNT Libraries Government Documents Department
open access

A perspective on progress in liquid metal reactor safety

Description: Changes in perspectives on fast reactor safety have occurred over the past ten years due both to technical progress and to the course of events. The major aspect of these changes is that they relate to basic design decisions that are largely, but not exclusively, related to safety considerations. Among the topics discussed are inherent safety, choice of fuel between metal and oxide, choice of reactor configuration between pool and loop, impact of size on safety characteristics and modularity, c… more
Date: January 1, 1990
Creator: Avery, R.
Partner: UNT Libraries Government Documents Department
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