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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
open access

Cost of NEPA Alternatives

Description: "The objective of this study is to provide an up-to-date documentation of the costs of nuclear electrical generating plants as they relate to site characteristics, in the following areas and systems: Main condenser cooling systems, Transmission, Site access, Food Protection, Plant site earthwork."
Date: August 1981
Partner: UNT Libraries Government Documents Department
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Power Burst Facility (PBF) Severe Fuel Damage Test 1-4: Test Results Report

Description: "A description and evaluation of the major phenomena, based upon the response of on-line instrumentation, analysis of fission product and aerosol data, postirradiation examination of the fuel bundle, and calculations using the SCDAP/RELAP5 computer code, are presented"
Date: April 1989
Creator: Petti, D. A.; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R.; Hagrman, Donald L. et al.
Partner: UNT Libraries Government Documents Department
open access

The Beckman 7C Thermal Cell (Hydrogen Monitor) Experiments

Description: Report describing small-scale laboratory experiments using a Beckman model 7C thermal conductivity cell conducted in order to provide a better understanding of the response of the hydrogen monitor during Power Burst Facility (PDF) Severe Fuel Damage (SFD) tests (p. 1).
Date: April 1989
Creator: Petti, D. A.; Carboneau, M. L; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R. et al.
Partner: UNT Libraries Government Documents Department
open access

Experiment Data Report for Multirod Burst Test (MRBT) Bundle B-5

Description: "This report presents, in considerable detail, the experimental data for the B-5 test conducted by the Multirod Burst Test (MRBT) Program at Oak Ridge National Laboratory."
Date: August 1984
Creator: Chapman, R. H.; Crowley, J. L. & Longest, A. W.
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
open access

COPS Model Estimates of LLEA Availability Near Selected Reactor Sites

Description: "The COPS computer model has been used to estimate local law enforcement agency (LLAE) officer availability in the neighborhood of selected nuclear reactor sites. The results of these analyses are presented both in graphic and tabular form in this report."
Date: July 1980
Creator: Berkbigler, K. 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

The DF-4 Fuel Damage Experiment in ACRR With a BWR Control Blade and Channel Box

Description: "In addition to BWR background information, this document contains a description of the experimental hardware with details on how the experiment was instrumented and diagnosed, a description of the test progression, and a presentation on the on-line instruments."
Date: November 1989
Creator: Gauntt, Randall Owen; Gasser, R. D. & Ott, L. J.
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
open access

Reactivity Initiated Accident Test Series Test RIA 1-4 Fuel Behavior Report

Description: "This report presents and discusses the results from the final test in the Reactivity Initiated Accident (RIA) Test Series, Test RIA 1-4, conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory." from Abstract
Date: September 1984
Creator: Cook, Beverly A. & Martinson, Zoel R.
Partner: UNT Libraries Government Documents Department
open access

Appendix A. Test Design and Configuration

Description: "This appendix summarizes the design of the [Power Burst Facility] PBF test rods and test train hardware, and the rod assembly instrumentation" for Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho. (p. A-2)
Date: September 1984
Creator: Cook, Beverly A. & Martinson, Zoel R.
Partner: UNT Libraries Government Documents Department
open access

Appendix B. Test Conduct

Description: This appendix describes the operational phases of the Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho.
Date: September 1984
Creator: Cook, Beverly A. & Martinson, Zoel R.
Partner: UNT Libraries Government Documents Department
open access

Appendix C: Data Qualification, Uncertainties, and Data Plots

Description: "This appendix describes the Test RIA 1-4 data qualification procedures, methods for evaluating uncertainties, and detailed plots of qualified data." (p. C-2) The report discusses test design and configuration; test conduct; data qualification, uncertainties, and data plots; fuel rod analysis; pre- and post test nondestructive and destructive examination results; reactor physics analysis; and document and records traceability for Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test… more
Date: September 1984
Creator: Cook, Beverly A. & Martinson, Zoel R.
Partner: UNT Libraries Government Documents Department
open access

Appendix D. Fuel Rod Analysis

Description: Appendix providing analysis for fuel rod behavior for Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho.
Date: September 1984
Creator: Cook, Beverly A. & Martinson, Zoel R.
Partner: UNT Libraries Government Documents Department
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Appendix E: Pre- and Postest Nondestructive and Desctructive Examination Results

Description: This appendix documents [nondestructive and destructive examinations and pretest data for for Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test flow shroud removed after a test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho.
Date: September 1984
Creator: Cook, Beverly A. & Martinson, Zoel R.
Partner: UNT Libraries Government Documents Department
open access

Appendix F: Reactor Physics Analysis

Description: Analysis for reactor physics for Reactivity Initiated Accident (RIA) Series 1-4 fuel behavior test conducted at the Idaho National Engineering Laboratory in Idaho Falls, Idaho.
Date: September 1984
Creator: Cook, Beverly A. & Martinson, Zoel R.
Partner: UNT Libraries Government Documents Department
open access

Appendix G: Document and Records Traceability

Description: "This appendix (a) provides a description of documentation and computer tapes generated while preparing for, conducing, and gathering data from Test RIA 1-4 at the Power Burst Facility (PBF); (b) provides a list of some primary documents; and (c) describes how to obtain finished data and some primary documents." (p. G-2)
Date: September 1984
Creator: Cook, Beverly A. & Martinson, Zoel R.
Partner: UNT Libraries Government Documents Department
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