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Evaluating Strength and Ductility of Irradiated Zircaloy, Task 5: Experimental Data, Final Report (open access)

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

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.
Object Type: Report
System: The UNT Digital Library
Evaluation of trench subsidence and stabilization at Sheffield low-level radioactive waste disposal facility : Sheffield, Illinois, final report, October 15, 1980-March 30, 1981 (open access)

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

"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.
Object Type: Report
System: The UNT Digital Library
[Appendix A. Pretest Fuel Rod Component and Instrumentation Characterization (PCM-5)] (open access)

[Appendix A. Pretest Fuel Rod Component and Instrumentation Characterization (PCM-5)]

Appendix to report "Test PCM-5 Fuel Rod Materials Behavior" presenting pretest physical characteristics of the Power-Cooling-Mismatch Test Series PCM-5 fuel rod components.
Date: May 1980
Creator: Kerwin, Deborah K.
Object Type: Report
System: The UNT Digital Library
Appendix B. Fuel Rod Axial Power Profiles (open access)

Appendix B. Fuel Rod Axial Power Profiles

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.
Object Type: Report
System: The UNT Digital Library

Appendix C. Postest Bundle and Individual Fuel Rod Overall Photographs

Appendix presenting postest bundle and individual fuel rod photographs for report "Test PCM-5 Fuel Rod Materials Behavior."
Date: May 1980
Creator: Kerwin, Deborah K.
Object Type: Dataset
System: The UNT Digital Library
Appendix D. Postest Rod-to-Rod Spacing Measurements And Individual Rod Diameter Measurements (open access)

Appendix D. Postest Rod-to-Rod Spacing Measurements And Individual Rod Diameter Measurements

Report presenting rod-to-rod spacing measurements and individual rod diameter measurements for fuel rods used in the Power-Cooling-Mismatch Test Series PCM-5.
Date: May 1980
Creator: Kerwin, Deborah K.
Object Type: Report
System: The UNT Digital Library
Test PCM-5 Fuel Rod Materials Behavior (open access)

Test PCM-5 Fuel Rod Materials Behavior

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.
Object Type: Report
System: The UNT Digital Library
Appendix E. Fuel Rod Sectioning and Metallographic Examinations (open access)

Appendix E. Fuel Rod Sectioning and Metallographic Examinations

Report presenting preparation of the Power-Cooling-Mismatch Test Series PCM-5 fuel rods and fuel rod sections for metallographic examination and the metallographic examination results from Rods 205-1, -2, -3, -4, -5, -6, and -8.
Date: May 1980
Creator: Kerwin, Deborah K.
Object Type: Report
System: The UNT Digital Library
Appendix I. Scanning Electron Microscope Examination of Rod 205-4 Cladding Fracture Surface (open access)

Appendix I. Scanning Electron Microscope Examination of Rod 205-4 Cladding Fracture Surface

Report presenting scanning electron microscopy (SEM) examinations used to analyze one cladding fracture surface of Rod 205-4 for Power-Cooling-Mismatch Test Series PCM-5.
Date: May 1980
Creator: Kerwin, Deborah K.
Object Type: Report
System: The UNT Digital Library
Appendix H. Fuel Rod Particle Size Analyses (open access)

Appendix H. Fuel Rod Particle Size Analyses

Report presenting fuel rod particle sizes and size distributions as determined for the two failed Test PCM-5 fuel rods.
Date: May 1980
Creator: Kerwin, Deborah K.
Object Type: Report
System: The UNT Digital Library
Appendix F. Fuel Rod Temperature Estimates (open access)

Appendix F. Fuel Rod Temperature Estimates

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.
Object Type: Report
System: The UNT Digital Library
Appendix G. Microprobe Examinations (open access)

Appendix G. Microprobe Examinations

Report presenting microprobe examination results of fuel Rods 205-1, 205-2, and 205-8 for test Power-Cooling-Mismatch Test Series PCM-5.
Date: May 1980
Creator: Kerwin, Deborah K.
Object Type: Report
System: The UNT Digital Library
An approach to seismic zonation for siting nuclear electric power generating facilities in the eastern United States (open access)

An approach to seismic zonation for siting nuclear electric power generating facilities in the eastern United States

"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.
Object Type: Report
System: The UNT Digital Library
Evaluating Strength and Ductility of Irradiated Zircaloy, Task 5: Mathematical-Model Development, Final Report (open access)

Evaluating Strength and Ductility of Irradiated Zircaloy, Task 5: Mathematical-Model Development, Final Report

MAthematical-modeling studies were carried out to determine effects of isothermal and anisothermal anneals on recovery of mechanical properties of irradiated Zircaloy.
Date: May 1981
Creator: Lowry, L. M.; Markworth, A. J.; Perrin, J. S. & Landow, M. P.
Object Type: Report
System: The UNT Digital Library
Loss-of-Coolant Accident Test Series -- Results of TC-1 Tests (open access)

Loss-of-Coolant Accident Test Series -- Results of TC-1 Tests

The results of an in-pile nuclear blowdown test series, designated TC-1, are presented in this report.
Date: May 1981
Creator: Yackle, Tom R.; Waterman, Michael E. & MacDonald, Philip E.
Object Type: Report
System: The UNT Digital Library
Appendix A: Additional Plots For Tests TC-1B, TC-1C, and TC-1D (open access)

Appendix A: Additional Plots For Tests TC-1B, TC-1C, and TC-1D

Graphs plotting the thermal-hydraulic response of the TC-1 tests characterized by the system depressurization, volumetric flow, temperature (in Kelvin) over time within each fuel rod flow shroud used in the study.
Date: May 1981
Creator: Yackle, Tom R.; Waterman, Michael E. & MacDonald, Philip E.
Object Type: Report
System: The UNT Digital Library
Appendix B: Thermal-Hydraulic Data Related To TC-1 Tests (open access)

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

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.
Object Type: Report
System: The UNT Digital Library
Appendix C: Fuel Rod Characterization (open access)

Appendix C: Fuel Rod Characterization

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.
Object Type: Report
System: The UNT Digital Library
Appendix D: Experiment Design and Conduct (open access)

Appendix D: Experiment Design and Conduct

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.
Object Type: Report
System: The UNT Digital Library