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Evaluating Strength and Ductility of Irradiated Zircaloy, Task 5: Experimental Data, Final Report

Description: The objective of this program was to provide a mechanical-property database that could be used to predict the performance of Zircaloy cladding under various off-normal, transient, and accident conditions in a power reactor.
Date: May 1981
Creator: Lowry, L. M.; Markworth, A. J.; Perrin, J. S. & Landow, M. P.
Partner: UNT Libraries Government Documents Department
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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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An approach to seismic zonation for siting nuclear electric power generating facilities in the eastern United States

Description: "This report describes a systematic study to determine the relationship between seismicity and geologic or geophysical features for the central and eastern United States in order to delineate seismic hazard."
Date: May 1981
Creator: Barstow, N. L.; Brill, K. G.; Nuttli, Otto W. & Pomeroy, P. W.
Partner: UNT Libraries Government Documents Department
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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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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. Fuel Rod Temperature Estimates

Description: Report presenting cladding axial and circumferential temperature estimates, fuel rod radial temperature estimates, and the techniques used to estimate the cladding and fuel temperatures for Power-Cooling-Mismatch Test Series PCM-5.
Date: May 1980
Creator: Kerwin, Deborah K.
Partner: UNT Libraries Government Documents Department
open access

Appendix B: Thermal-Hydraulic Data Related To TC-1 Tests

Description: Graphs presenting peak power history, ratio of local rod power to rod average power (P/A), total heat transfer coefficient history, and coolant pressure history conditions in the test assembly during the transient phase of the TC-1 tests.
Date: May 1981
Creator: Yackle, Tom R.; Waterman, Michael E. & MacDonald, Philip E.
Partner: UNT Libraries Government Documents Department
open access

Appendix C: Fuel Rod Characterization

Description: Tables presenting design variables for TC-1 fuel rods including composite powder analysis, pellet and fuel stack dimensions, and fuel rod and flow shroud dimensions.
Date: May 1981
Creator: Yackle, Tom R.; Waterman, Michael E. & MacDonald, Philip E.
Partner: UNT Libraries Government Documents Department
open access

Appendix D: Experiment Design and Conduct

Description: Report presenting the design of the Test TC-1 test train and Power Burst Facility (PBF) blowdown system and the test conduct in tables, text, and illustrations.
Date: May 1981
Creator: Yackle, Tom R.; Waterman, Michael E. & MacDonald, Philip E.
Partner: UNT Libraries Government Documents Department
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