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Evaluation of trench subsidence and stabilization at Sheffield low-level radioactive waste disposal facility : Sheffield, Illinois, final report, October 15, 1980-March 30, 1981

Description: "This report presents the results of the evaluation of trench subsidence and possible future stabilization techniques at the Sheffield Low-Level Radioactive Waste Disposal Facility, Sheffield, Illinois."
Date: May 1981
Creator: Kahle, R. & Rowlands, J.
Partner: UNT Libraries Government Documents Department
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Nuclear Power Plant Fire Protection

Description: This report examines the adequacy of existing fire-hazards analysis methodology in the context of nuclear power plant safety
Date: September 1979
Creator: Berry, Dennis L. & Minor, Earl E.
Partner: UNT Libraries Government Documents Department
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SABRES II: Code Description and Users Manual

Description: SABRES II is an individual resolution computer simulation of combat between two small groups using small arms weapons.
Date: March 1980
Creator: De Laquil, Pascal
Partner: UNT Libraries Government Documents Department
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Power Plant Staffing

Description: This report discusses the results of a comparative review of the selection, training, qualification, and requalification of Maitenncace personnel, operators, shift supervisors, and senior onsite managers involved in the operation and/or maintenance of nuclear power plants.
Date: March 1980
Creator: Wegner, W.
Partner: UNT Libraries Government Documents Department
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Bouguer Gravity Anomaly Map of the East-Central Midcontinent of the United States: New Madrid Seismotectonic Study Group

Description: The purposes of this report are to document the data sources and the procedures used in the reduction of the data and to present a Bouguer gravity anomaly map derived from the data set.
Date: October 1980
Creator: Keller, G. Randy; Russell, D. R.; Hinze, William J.; Reed, J. E. & Geraci, Philip J.
Partner: UNT Libraries Government Documents Department
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Compilation, Assessment and Expansion of the Strong Earthquake Ground Motion Data Base: Seismic Margins Research Program (SSMRP)

Description: A catalog had been prepared which contains information for world-wide, ground-motion accelerograms, the accelerogaph sites where these records were obtained, and the seismological parameters of the causative earthquakes.
Date: September 1980
Creator: Crouse, C. B.; Hileman, J. A.; Turner, B. E. & Martin, G. R.
Partner: UNT Libraries Government Documents Department
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Appendix E. Post Irradiation Examination Results

Description: Report presenting the results of nondestructive and destructive examinations of four fuel rods from Test RIA 1-2.
Date: January 1981
Creator: Cook, Beverly A.; Fukuda, Steven K.; Martinson, Zoel R. & Bott-Hembree, Patricia
Partner: UNT Libraries Government Documents Department
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Appendix F. Wizard Code

Description: Report detailing the computer code used to calculate the cladding temperatures (WIZARD code) from the observed oxidation of the cladding for Test RIA 1-2.
Date: January 1981
Creator: Cook, Beverly A.; Fukuda, Steven K.; Martinson, Zoel R. & Bott-Hembree, Patricia
Partner: UNT Libraries Government Documents Department
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Reactivity Initiated Accident Test Series Test RIA 1-2 Fuel Behavior Report

Description: This report presents and discusses the results from the Reactivity Initiated Accident Test RIA1-2 conducted in the Power Burst Facility at the Idaho National Engineering Laboratory.
Date: January 1981
Creator: Cook, Beverly A.; Fukuda, Steven K.; Martinson, Zoel R. & Bott-Hembree, Patricia
Partner: UNT Libraries Government Documents Department
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Appendix B. Test PCM-3 Instrumentation and Associated Uncertainties

Description: Appendix to Test PCM-3 report presenting a description of the "instrumentation and the calibration equations that were used to convert the transducer output to engineering units during the data reduction process." (p. 61)
Date: August 1979
Creator: Owen, Dennis E. & Vinjamuri, Krishna
Partner: UNT Libraries Government Documents Department
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[Appendix C. Test PCM-3 Fuel Rod Power Calibration]

Description: Report presenting the results of thermal heat balance power calibration and neutron flux axial distribution measurements for the Power-Cooling-Mismatch Test PCM-3.
Date: August 1979
Creator: Owen, Dennis E. & Vinjamuri, Krishna
Partner: UNT Libraries Government Documents Department
open access

[Appendix D. Test PCM-3 Data Plots]

Description: Report presenting data plots for selected parameters measured during Test PCM-3 of the Power-Cooling-Mismatch Test Series.
Date: August 1979
Creator: Owen, Dennis E. & Vinjamuri, Krishna
Partner: UNT Libraries Government Documents Department
open access

Appendix A. Pretest Fuel Rod Characterization

Description: Report presenting pretest characterization measurements for two of the four Power-Cooling Mismatch Test PCM-3 fuel rods, Rods UTA-0011 and UTA-0013.
Date: August 1979
Creator: Owen, Dennis E. & Vinjamuri, Krishna
Partner: UNT Libraries Government Documents Department
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[Appendix E. Comparison of Calculated and Measured Fuel Rod Behavior for Test PCM-3]

Description: Report to appendix presenting a comparison of the calculated and measured fuel rod behavior determined during steady state power calibration, the onset of departure from nucleate boiling (DNB), and post-DNB test for Power-Cooling Mismatch Test PCM-3. (p. 155)
Date: August 1979
Creator: Owen, Dennis E. & Vinjamuri, Krishna
Partner: UNT Libraries Government Documents Department
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Appendix B. Fuel Rod Axial Power Profiles

Description: Report presenting details of Test-PCM-5 fuel rod axial power profiles as determined by two methods: gamma scanning of the fuel bundle flux wires and radiochemical burnup analysis of fuel samples from Rods 205-1, -2, -3, -5, -7, -8, and -9. (p. B-2)
Date: May 1980
Creator: Kerwin, Deborah K.
Partner: UNT Libraries Government Documents Department
open access

[Appendix F. Cladding Surface Temperature Estimates (Test PCM-3)]

Description: Report presenting estimates of the methods used to establish fuel rod cladding temperatures for Test PCM-3 using three techniques: metallographic examination of the cladding microstructures, isothermal reaction rate correlations, and BUILD5 computer code calculations.
Date: August 1979
Creator: Owen, Dennis E. & Vinjamuri, Krishna
Partner: UNT Libraries Government Documents Department
open access

Test PCM-5 Fuel Rod Materials Behavior

Description: Test PCM-5 was the first nine-rod bundle test in the Power-Cooling-Mismatch (PCM) Test Series. The test objectives were to evaluate the behavior of the center rod operated in an environment typical of a commercial reactor rod subjected to PCM transient and to investigate the potential for rod-to-rod interactions.
Date: May 1980
Creator: Kerwin, Deborah K.
Partner: UNT Libraries Government Documents Department
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