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Geologic and hydrologic research at the Western New York Nuclear Service Center, West Valley, New York: final report

Description: "This report is the last in a series by the New York State Geological Survey on studies funded by the U.S. Nuclear Regulatory Commission. The report covers five important aspects of the geology and hydrology of the Western New York Nuclear Service Center, near West Valley, New York: geomorphology, stratigraphy, sedimentology, surface water, and radionuclide analyses. We reviewed past research on these subjects and present new data obtained in the final phase of NYSGS research at the site. Also … more
Date: June 1984
Creator: Albanese, J. R.; Anderson, S. L.; Fakundiny, Robert H.; Potter, S. M.; Rogers, W. B. & Whitbeck, L. F.
Partner: UNT Libraries Government Documents Department
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Fuel Rod Material Behavior During Test PCM-1

Description: This report presents the analysis of the fuel rod materials behavior based on the postirradiation examination of the Test PCM-1 fuel rod from the Power-Cooling-Mismatch Test Series.
Date: June 1979
Creator: Cook, Beverly A.
Partner: UNT Libraries Government Documents Department
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Appendix G. U0₂ Oxidation Calculation

Description: Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including the U0₂ oxidation calculation.
Date: June 1979
Creator: Cook, Beverly A.
Partner: UNT Libraries Government Documents Department
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Appendix F. Cladding Thermal Conductivity Changes

Description: Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including changes in cladding thermal conductivity with oxidation to ZrO₂.
Date: June 1979
Creator: Cook, Beverly A.
Partner: UNT Libraries Government Documents Department
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Appendix C. Metallographic Examination

Description: Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including additional metallography illustrating the physical and chemical changes in the cladding and fuel.
Date: June 1979
Creator: Cook, Beverly A.
Partner: UNT Libraries Government Documents Department
open access

Appendix D. Particle Size Analysis

Description: Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including tabulated data from the particle size analysis of the broke fuel rod pieces.
Date: June 1979
Creator: Cook, Beverly A.
Partner: UNT Libraries Government Documents Department
open access

Appendix B. Test Rod Power Profile

Description: Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including a description of the axial power profile.
Date: June 1979
Creator: Cook, Beverly A.
Partner: UNT Libraries Government Documents Department
open access

Appendix E. Microprobe Examination

Description: Appendix to report presenting detailed data from the postirradiation examination and pretest characterization for Test PCM-1, including details of the microprobe examination.
Date: June 1979
Creator: Cook, Beverly A.
Partner: UNT Libraries Government Documents Department
open access

Experiment Data Report for Test RIA 1-2

Description: "Recorded test data are presented for the second of six planned tests in the Reactivity Initiated Accident (RIA) Test Series 1, Test RIA 1-2. This Test, conducted at the Power Burst Facility, had the following objectives: (1) Characterize the response of preirradiated fuel rods during an RIA event conducted at boiling water reactor hot-startup conditions. (2) Evaluate the effect of rod internal pressure on preirradiated fuel rod response during an RIA event."
Date: June 1979
Creator: Zimmermann, Carolyn L.; White, Christine E. & Evans, Robert P.
Partner: UNT Libraries Government Documents Department
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Experiment Data Report for Multirod Burst Test (MRBT) Bundle B-6

Description: A report regarding experiment data for a multirod burst test, to investigate cladding deformation in the alpha-plus-beta-Ziracloy temperature range under light-water-reactor (LWR) loss-of-coolant accident (LOCA) conditions."
Date: June 11, 1984
Creator: Chapman, R. H.; Longest, A. W. & Crowley, J. L.
Partner: UNT Libraries Government Documents Department
open access

An Analytical Study of Seismic Threat to Containment Integrity

Description: Report providing quantitative information of containment seismic capacity considering a rather complete list of limit states along with a discussion of factors that are significant for determining seismic capacity and recommendations for future work.
Date: June 1989
Creator: Amin, M.; Agrawal, P. K. & Ahl, T. J.
Partner: UNT Libraries Government Documents Department
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