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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

[Appendix I-SCDAP/RELAP5 Analysis Model Code Calculations]

Description: Code calculations associated with Analysis of Test Severe Fuel Damage (SFD) 1-3 "performed with Quality Assured Version 251 of the SCDAP/RELAP5/MOD2 code, which is a computer code designed to characterize and quantify fuel damage processes in a reactor vessel during severe accidents. The code can be applied to the analysis of an individual fuel bundle, such as is the case for Test SFD 1-3, or to the analysis of an entire primary coolant system." (Page I-3 of the report)
Date: October 1989
Creator: Martinson, Zoel R.; Gasparini, M.; Hobbins, Richard R.; Petti, D. A.; Allison, C. M.; Hohorst, J. K. et al.
Item Type: Refine your search to only Dataset
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

[Appendix C-DARS Data Plots from Test SFD 1-4]

Description: Graphs showing plots of the qualified Power Burst Facility (PBF) Data Acquisition and Reduction System (DARS) data from Test Severe Fuel Damage (SFD) 1-4 performed at the Idaho National Engineering Laboratory. Qualified data is shown as a solid line and trend data appears as a dashed line (see page C-16 of report). Time (in seconds) appears on the x-axis and pressure (MPa) appears on the y-axis.
Date: April 1989
Creator: Petti, D. A.; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R.; Hagrman, Donald L. et al.
Item Type: Refine your search to only Dataset
Partner: UNT Libraries Government Documents Department

[Appendix J-SCDAP/RELAP5 Analysis Model: Code Calculations]

Description: Document listing code calculations used for SCDAP/RELAP5 models, which has been designed to characterize fuel damage processes in a reactor vessel during severe accidents (see pages J-1 to J-4 of report).
Date: April 1989
Creator: Petti, D. A.; Martinson, Zoel R.; Hobbins, Richard R.; Allison, C. M.; Carlson, E. R.; Hagrman, Donald L. et al.
Item Type: Refine your search to only Dataset
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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