Power-Cooling-Mismatch Test Series: Test PCM-3 Test Results Report (open access)

Power-Cooling-Mismatch Test Series: Test PCM-3 Test Results Report

A report presenting the results from Power-Cooling-Mismatch Test CM-3
Date: August 1979
Creator: Owen, Dennis E. & Vinjamuri, Krishna
Object Type: Report
System: The UNT Digital Library
Nuclear Power Plant Fire Protection (open access)

Nuclear Power Plant Fire Protection

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.
Object Type: Report
System: The UNT Digital Library
Experiment Data Report for PBF/LOFT Lead Rod Test Series: (Tests LLR-S0, -3, -4, -4A, and -5) (open access)

Experiment Data Report for PBF/LOFT Lead Rod Test Series: (Tests LLR-S0, -3, -4, -4A, and -5)

This report presents recorded test data for Tests LLR-S0, LLR-3, LLR-4A, and LLR-5 of the thermal Fuels Behavior Program PBF/LOFT Lead Rod Test Series.
Date: October 1979
Creator: Buckland, Russell J. & Schwieder, David H.
Object Type: Report
System: The UNT Digital Library

[Power Calibration and Preconditioning Data Plots]

Power calibration and preconditioning data plots for PBF/LOFT Lead Rod Test Series, indicating the time after start of power calibration in hours with each variable.
Date: October 1979
Creator: Buckland, Russell J. & Schwieder, David H.
Object Type: Dataset
System: The UNT Digital Library
Errata sheet for Geomorphic and erosion studies at the Western New York Nuclear Service Center, West Valley, New York (open access)

Errata sheet for Geomorphic and erosion studies at the Western New York Nuclear Service Center, West Valley, New York

An errata sheet for geomorphic and erosion studies at the Western New York Nuclear Service Center West Valley, New York.
Date: February 26, 1980
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Power Plant Staffing (open access)

Power Plant Staffing

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.
Object Type: Report
System: The UNT Digital Library
SABRES II: Code Description and Users Manual (open access)

SABRES II: Code Description and Users Manual

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
Object Type: Report
System: The UNT Digital Library

[SABRES II: Code Description and Users Manual, Appendix D: Code Listing]

The following data provides the code for the SABRES II model.
Date: March 1980
Creator: De Laquil, Pascal
Object Type: Dataset
System: The UNT Digital Library

[Dynamic Testing Data]

Dynamic test data from an experiment conducted to determine the puncture resistance of lead- and uranium-backed type AISI 316 stainless steel (SS) plates. The data is presented in line graphs. The parameters that were varied in this investigation were punch diameter, test plate thickness, backing material, and test temperature.
Date: April 1980
Creator: Larder, R. & Arthur, D.
Object Type: Dataset
System: The UNT Digital Library
Puncture of Shielded Radioactive Material Shipping Containers (open access)

Puncture of Shielded Radioactive Material Shipping Containers

Report on the development of improved analytical methods for predicting puncture of radioactive material shipping containers.
Date: April 1980
Creator: Larder, R. & Arthur, D.
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
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 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
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 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
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. Extended Analysis Microfiche]

Graphical presentations of data from the 1/5-scale Mark I BWR Pressure Suppression Experiment (PSE) air transient tests, including HVLF Characterization Data, Impulse Characterization, Computed Load Cell Response Histories and Frequency Analyses, and Enthalpy Flux Evaluation (see Table E-1. Summary of microfiche descriptions)
Date: June 1980
Creator: Lawrence Livermore National Laboratory
Object Type: Dataset
System: The UNT Digital Library
Extended Analysis of Data From the 1/5-Scale Mark I Boiling Water Reactor Pressure Suppression Experiment (open access)

Extended Analysis of Data From the 1/5-Scale Mark I Boiling Water Reactor Pressure Suppression Experiment

A report regarding results of an extended analysis of data from a 1/5-scale Mark I boiling water reactor pressure suppression experiment.
Date: June 1980
Creator: McCauley, E. W.; Holman, Garry S.; Carr, E. W.; Lai, W. & Mellor, J. E.
Object Type: Report
System: The UNT Digital Library

[COPS Analysis Tables]

Tables presenting the results of COPS computer model analyses, which has been used to estimate local law enforcement agency (LLEA) officer availability in the neighborhood of 60 selected nuclear reactor sites. The tables show the unrestricted response and restricted response for both state and local police within a given radius for each neighborhood in the study (see page 10 of report).
Date: July 1980
Creator: Sandia Laboratories.
Object Type: Dataset
System: The UNT Digital Library
COPS Model Estimates of LLEA Availability Near Selected Reactor Sites (open access)

COPS Model Estimates of LLEA Availability Near Selected Reactor Sites

"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.
Object Type: Report
System: The UNT Digital Library