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Nuclear power plant Generic Aging Lessons Learned (GALL). Main report and appendix A

Description: The purpose of this generic aging lessons learned (GALL) review is to provide a systematic review of plant aging information in order to assess materials and component aging issues related to continued operation and license renewal of operating reactors. Literature on mechanical, structural, and thermal-hydraulic components and systems reviewed consisted of 97 Nuclear Plant Aging Research (NPAR) reports, 23 NRC Generic Letters, 154 Information Notices, 29 Licensee Event Reports (LERs), 4 Bullet… more
Date: December 1996
Creator: Kaza, K. E.; Diercks, D. R.; Holland, J. W. & Choi, S. U.
Partner: UNT Libraries Government Documents Department
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Real-time 3-D SAFT-UT system evaluation and validation

Description: SAFT-UT technology is shown to provide significant enhancements to the inspection of materials used in US nuclear power plants. This report provides guidelines for the implementation of SAFT-UT technology and shows the results from its application. An overview of the development of SAFT-UT is provided so that the reader may become familiar with the technology. Then the basic fundamentals are presented with an extensive list of references. A comprehensive operating procedure, which is used in co… more
Date: September 1, 1996
Creator: Doctor, S. R.; Schuster, G. J.; Reid, L. D. & Hall, T. E.
Partner: UNT Libraries Government Documents Department
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Analysis of Removal Alternatives for the Heavy Water Components Test Reactor at the Savannah River Site

Description: This engineering study was developed to evaluate different options for decommissioning of the Heavy Water Components Test Reactor (HWCTR) at the Savannah River Site. This document will be placed in the DOE-SRS Area reading rooms for a period of 30 days in order to obtain public input to plans for the demolition of HWCTR.
Date: August 1996
Creator: Owen, M. B.
Partner: UNT Libraries Government Documents Department
open access

Nuclear power plant Generic Aging Lessons Learned (GALL). Appendix B

Description: The purpose of this generic aging lessons learned (GALL) review is to provide a systematic review of plant aging information in order to assess materials and component aging issues related to continued operation and license renewal of operating reactors. Literature on mechanical, structural, and thermal-hydraulic components and systems reviewed consisted of 97 Nuclear Plant Aging Research (NPAR) reports, 23 NRC Generic Letters, 154 Information Notices, 29 Licensee Event Reports (LERs), 4 Bullet… more
Date: December 1996
Creator: Kasza, K. E.; Diercks, D. R.; Holland, J. W. & Choi, S. U.
Partner: UNT Libraries Government Documents Department
open access

Summary of failure analysis activities at Brookhaven National Laboratory

Description: Brookhaven National Laboratory has for many years conducted examinations related to the failures of nuclear materials and components. These examinations included the confirmation of root cause analyses, the determination of the causes of failure, identification of the species that accelerate corrosion, and comparison of the results of nondestructive examinations with those obtained by destructive examination. The results of those examinations, which had previously appeared in various formats (f… more
Date: October 1, 1996
Creator: Cowgill, M. G.; Czajkowski, C. J. & Franz, E. M.
Partner: UNT Libraries Government Documents Department
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Review criteria for ARC ALWR equipment qualification

Description: Advanced Reactor Corporation has developed a methodology for seismic qualification of equipment in Advanced Light Water Reactor plants by use of experience data. The exiting criteria for review of seismic qualification available in the industry standards and NRC Regulatory Guides and Standard Review Plans are inadequate for this purpose. This paper presents an alternative framework and a set of criteria that can be used for review of the ARC qualification methodology.
Date: December 31, 1996
Creator: Bandyopadhyay, K.K.
Partner: UNT Libraries Government Documents Department
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Prodiag--a hybrid artificial intelligence based reactor diagnostic system for process faults

Description: Commonwealth Research Corporation (CRC) and Argonne National Laboratory (ANL) are collaborating on a DOE-sponsored Cooperative Research and Development Agreement (CRADA), project to perform feasibility studies on a novel approach to Artificial Intelligence (Al) based diagnostics for component faults in nuclear power plants. Investigations are being performed in the construction of a first-principles physics-based plant level process diagnostic expert system (ES) and the identification of compon… more
Date: March 1, 1996
Creator: Reifman, J.; Wei, T. Y. C.; Vitela, J. E.; Applequist, C. A. & Chasensky, T. M.
Partner: UNT Libraries Government Documents Department
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The D&D of the Experimental Boiling Water Reactor (EBWR)

Description: Argonne National Laboratory has completed the D&D of the Experimental Boiling Water Reactor. The Project consisted of decontaminating and for packaging as radioactive waste the reactor vessel and internals, contaminated piping systems, miscellaneous tanks, pumps, and associated equipment. The D&D work involved dismantling process equipment and associated plumbing, ductwork drain lines, etc., performing size reduction of reactor vessel internals in the fuel pool, packaging and manifesting all ra… more
Date: March 1, 1996
Creator: Fellhauer, C. R.; Boling, L. E.; Yule, T. J. & Bhattacharyya, S. K.
Partner: UNT Libraries Government Documents Department
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Corrosion Fatigue Crack Growth in Clad Low-Alloy Steels: Part 1, Medium-Sulfur Forging Steel

Description: Corrosion fatigue crack propagation tests were conducted on a medium- sulfur ASTM A508-2 forging steel overlaid with weld-deposited Alloy EN82H cladding. The specimens featured semi-elliptical surface cracks penetrating approximately 6.3 mm of cladding into the underlying steel. The initial crack sizes were relatively large with surface lengths of 30.3--38.3 mm, and depths of 13.1--16.8 mm. The experiments were conducted in a quasi-stagnant low-oxygen (O{sub 2} < 10 ppb) aqueous environment at … more
Date: April 1, 1996
Creator: James, L. A.; Poskie, T. J.; Auten, T. A. & Cullen, W. H.
Partner: UNT Libraries Government Documents Department
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A proposed acceptance process for commercial off-the-shelf (COTS) software in reactor applications

Description: This paper proposes a process for acceptance of commercial off-the-shelf (COTS) software products for use in reactor systems important to safety. An initial set of four criteria establishes COTS software product identification and its safety category. Based on safety category, three sets of additional criteria, graded in rigor, are applied to approve/disapprove the product. These criteria fall roughly into three areas: product assurance, verification of safety function and safety impact, and ex… more
Date: March 1, 1996
Creator: Preckshot, G.G. & Scott, J.A.
Partner: UNT Libraries Government Documents Department
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Material degradation analysis and maintenance decisions based on material condition monitoring during in-service inspections

Description: The degradation of the material in critical components is shown to be an effective measure which can be used to compute the risk adjusted economic penalty associated with different maintenance decisions. The approach of estimating the probability, with confidence interval, of the time that a prescribed degradation level is exceeded is shown to be practical, as demonstrated in the analysis of irradiated fuel cladding. The methodology for the estimation of the probability is predicated on the exi… more
Date: March 1, 1996
Creator: Yacout, A. M. & Orechwa, Y.
Partner: UNT Libraries Government Documents Department
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Performance of the CEDS Accident Dosimetry System at the 1995 Los Alamos National Laboratory Nuclear Accident Dosimetry Intercomparison

Description: In July 1995, LANL hosted an accident dosimetry intercomparison. When all reactors on the Oak Ridge Reservation were idled in 1988, the Health Physics Research Reactor (HPRR), which had been used for 22 previous intercomparisons dating from 1965, was shut down for an indefinite period. The LANL group began characterization of two critical assemblies for dosimetry purposes. As a result, NAD-23 was conceived and 10 DOE facilities accepted invitations to participate in the intercomparison. This re… more
Date: December 1, 1996
Creator: McMahan, K.L. & Schwanke, L.J.
Partner: UNT Libraries Government Documents Department
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Surplus weapons-grade plutonium: a resource for exploring and terraforming Mars

Description: With the end of the Cold War, greater than 100 metric tons (MT) of weapons-grade plutonium (WGPu) have become surplus to defense needs in the United States and the Former Soviet Union. This paper is a proposal for an option for WGPu disposition, i.e., use of the plutonium as a fuel for nuclear reactors for Mars exploration and eventual terraforming. WGPu was used in nuclear weapons because it has a much smaller critical mass than highly enriched uranium, allowing lighter weapons with consequent… more
Date: December 31, 1996
Creator: Muscatello, A.C. & Houts, M.G.
Partner: UNT Libraries Government Documents Department
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Prediction of stainless steel activation in experimental breeder reactor 2 (EBR-II) reflector and blanket subassemblies

Description: Stainless steel structural components in nuclear reactors become radioactive wastes when no longer useful. Prior to disposal, certain physical attributes must be analyzed. These attributes include structural integrity, chemical stability, and the radioactive material content among others. The focus of this work is the estimation of the radioactive material content of stainless steel wastes from a research reactor operated by Argonne National Laboratory.
Date: December 31, 1996
Creator: Bunde, K.A.
Partner: UNT Libraries Government Documents Department
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Remote dismantlement activities for the Argonne CP-5 Research Reactor

Description: The Department of Energy`s (DOE`s) Robotics Technology Development Program (RTDP) is participating in the dismantlement of a mothballed research reactor, Chicago Pile Number 5 (CP-5), at Argonne National Laboratory (ANL) to demonstrate technology developed by the program while assisting Argonne with their remote system needs. Equipment deployed for CP-5 activities includes the dual-arm work platform (DAWP), which will handle disassembly of reactor internals, and the RedZone Robotics-developed `… more
Date: December 31, 1996
Creator: Noakes, M.W.
Partner: UNT Libraries Government Documents Department
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Furfural-based polymers for the sealing of reactor vessels dumped in the Arctic Kara Sea

Description: Between 1965 and 1988, 16 naval reactor vessels were dumped in the Arctic Kara Sea. Six of the vessels contained spent nuclear fuel that had been damaged during accidents. In addition, a container holding {approximately} 60% of the damaged fuel from the No. 2 reactor of the atomic icebreaker Lenin was dumped in 1967. Before dumping, the vessels were filled with a solidification agent, Conservant F, in order to prevent direct contact between the seawater and the fuel and other activated componen… more
Date: October 7, 1996
Creator: Heiser, J. H.; Cowgill, M. G.; Sivintsev, Y. V.; Alexandrov, V. P. & Dyer, R. S.
Partner: UNT Libraries Government Documents Department
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Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, Tennessee Valley Authority. Supplement number 20

Description: This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), Supplement No. 8 (January 1992), Supplement No. 9 (June 1992), Supplement No. 10 (October 1992), Supplement No. 11 (April 1993), Supplement No. 12 (October 1993), Supplement No. 13 (A… more
Date: February 1, 1996
Partner: UNT Libraries Government Documents Department
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ORNL contribution to the IAEA bcnchmark problem on fission reactor decommissioning

Description: Recently the International Atomic Energy Agency (IAEA) selected a benchmark problem for calculation of radioactivity inventories and dose estimates necessary for fission reactor decommissioning. Several researchers were invited to participate in the solution of this benchmark problem set. The contribution from Oak Ridge National Laboratory (ORNL) is presented in this paper.
Date: May 1, 1996
Creator: Broadhead, B. L. & Childs, R. L.
Partner: UNT Libraries Government Documents Department
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Application of environmentally-corrected fatigue curves to nuclear power plant components

Description: Recent test data indicate that the effects of the light water reactor (LWR) environment could significantly reduce the fatigue resistance of materials used in the reactor coolant pressure boundary components of operating nuclear power plants. Argonne National Laboratory has developed interim fatigue curves based on test data simulating LWR conditions, and published them in NUREG/CR-5999. In order to assess the significance of these interim fatigue curves, fatigue evaluations of a sample of the … more
Date: June 1, 1996
Creator: Ware, A.G.; Morton, D.K. & Nitzel, M.E.
Partner: UNT Libraries Government Documents Department
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Reliability estimation for check valves and other components

Description: For years the nuclear industry has depended upon component operational reliability information compiled from reliability handbooks and other generic sources as well as private databases generated by recognized experts both within and outside the nuclear industry. Regrettably, these technical bases lacked the benefit of large-scale operational data and comprehensive data verification, and did not take into account the parameters and combinations of parameters that affect the determination of fai… more
Date: June 1, 1996
Creator: McElhaney, K.L. & Staunton, R.H.
Partner: UNT Libraries Government Documents Department
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ANL CP-5 decontamination and decommissioning project necessary and sufficient pilot. Report of the standards identification team on the selection of the necessary and sufficient standards set

Description: The CP-5 reactor was a heavy-water moderated and cooled, highly-enriched uranium-fueled thermal reactor designed for supplying neutrons for research. The reactor was operated almost continuously for 25 years until its final shutdown in 1979. It is situated on approximately three acres in the southwestern section of Argonne National Laboratory. In 1980, all nuclear fuel and the heavy water that could be drained from the process systems were shipped off-site, and the CP-5 facility was placed into… more
Date: May 1, 1996
Partner: UNT Libraries Government Documents Department
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Evidence of aging effects on certain safety-related components

Description: In response to interest shown by the Nuclear Energy Agency (NEA), Principal Working Group I (PWG- 1) of the Committee on the Safety of Nuclear Installations (CSNI) conducted a generic study on the effects of aging of active components in nuclear power plants. (This focus on active components is consistent with PWG-l`s mandate; passive components are primarily within the mandate of PWG-3.) Representatives from France, Sweden, Finland, Japan, the United States, and the United Kingdom participated… more
Date: January 1, 1996
Creator: Magleby, H. L.; Atwood, C. L.; MacDonald, P. E.; Edson, J. L. & Bramwell, D. L.
Partner: UNT Libraries Government Documents Department
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Evolutionary/advanced light water reactor data report

Description: The US DOE Office of Fissile Material Disposition is examining options for placing fissile materials that were produced for fabrication of weapons, and now are deemed to be surplus, into a condition that is substantially irreversible and makes its use in weapons inherently more difficult. The principal fissile materials subject to this disposition activity are plutonium and uranium containing substantial fractions of plutonium-239 uranium-235. The data in this report, prepared as technical inpu… more
Date: February 9, 1996
Partner: UNT Libraries Government Documents Department
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Corrosion fatigue crack growth in clad low-alloy steel. Part 2, Water flow rate effects in high sulfur plate steel

Description: Corrosion fatigue crack propagation tests were conducted on a high- sulfur ASTM A302-B plate steel overlaid with weld-deposited Alloy EN82H cladding. The specimens featured semi-elliptical surface cracks penetrating approximately 6.3 mm of cladding into the underlying steel. The initial crack sizes were relatively large with surface lengths of 22.8--27.3 mm, and depths of 10.5--14.1 mm. The experiments were initiated in a quasi-stagnant low-oxygen (O{sub 2} < 10 ppb) aqueous environment at 243{… more
Date: April 1, 1996
Creator: James, L. A; Lee, H. B.; Wire, G. L.; Novak, S. R. & Cullen, W. H.
Partner: UNT Libraries Government Documents Department
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