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[Appendix A. Pretest Fuel Rod Characteristics (PCM 8-1 RS, CHF Scoping, PCM 8-1 RF)]

Description: Report presenting pretest measurement characteristics of the fuel rods used in three, single-rod, power-cooling-mismatch tests: PCM 8-1 RS, CHF Scoping, and PCM 8-1 RF.
Date: November 1980
Creator: Johnson, Roger L.; Lassahn, Pamela L.; Martinson, Zoel R.; McCardell, Richard K.; Sparks, Daniel T. & MacDonald, Philip E.
Partner: UNT Libraries Government Documents Department
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Appendix B. Experiment Designs and Instrumentation

Description: Appendix detailing the hardware and instrumentation of test assemblies for the three single-rod Power-Cooling Mismatch (PCM) tests.
Date: November 1980
Creator: Johnson, Roger L.; Lassahn, Pamela L.; Martinson, Zoel R.; McCardell, Richard K.; Sparks, Daniel T. & MacDonald, Philip E.
Partner: UNT Libraries Government Documents Department
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Appendix E. Comparison of Calculated and Measured Fuel Rod Behavior

Description: "A comparison of the calculated and measured fuel rod behavior (cladding elongation, fuel centerline temperature, and fuel rod internal pressure) determined during the steady state power calibration, onset of departure from nucleate boiling (DNB), and post-DNB testing is presented in this appendix" (p. 184).
Date: August 1979
Creator: Johnson, Roger L.; Lassahn, Pamela L.; Martinson, Zoel R.; Sparks, Daniel T. & Schwieder, David H.
Partner: UNT Libraries Government Documents Department
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Appendix A. Pretest Fuel Rod Characteristics

Description: Report providing tabulated data for pretest measurements preformed to characterize three of the four Power-Cooling-Mismatch (PCM-4) fuel rods, Rods UTA-0014, UTA-0015, and UTA-0016.
Date: August 1979
Creator: Johnson, Roger L.; Lassahn, Pamela L.; Martinson, Zoel R.; Sparks, Daniel T. & Schwieder, David H.
Partner: UNT Libraries Government Documents Department
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Appendix A. Test PCM-1 Experiment Description

Description: Description of the test assembly and instrumentation used for Power-Cooling-Mismatch (PCM) Test Series, Test PCM-1 that includes a table and figures illustrating elements of the facility and test train assembly.
Date: August 1979
Creator: Sparks, Daniel T. & Stanley, Clifford J.
Partner: UNT Libraries Government Documents Department
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Appendix B. Rod Powers for Test PCM-1

Description: Description of the analytical methods and results for the Power-Cooling-Mismatch (PCM) Test Series, Test PCM-1.
Date: August 1979
Creator: Sparks, Daniel T. & Stanley, Clifford J.
Partner: UNT Libraries Government Documents Department
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Appendix C. FRAP-T4 Computer Code Model Description

Description: Report providing a description of the FRAP-T4 (Fuel Rod Analysis Program - Transient) computer code used for Power-Cooling-Mismatch (PCM) Test Series, Test PCM-1.
Date: August 1979
Creator: Sparks, Daniel T. & Stanley, Clifford J.
Partner: UNT Libraries Government Documents Department
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Appendix D. Pretest Fuel Rod Characterization Data

Description: Report presenting the pretest physical characterization data for the Power-Cooling-Mismatch (PCM) Test Series, Test PCM-1 fuel rod for use in model evaluation and posttest comparison. (p. 78)
Date: August 1979
Creator: Sparks, Daniel T. & Stanley, Clifford J.
Partner: UNT Libraries Government Documents Department
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Appendix C. Fuel Rod Power Calibration

Description: Report presenting the results of power calibration measurements and radiochemical analysis used to analyze and interpret Power-Cooling-Mismatch (Test PCM-4) data.
Date: August 1979
Creator: Johnson, Roger L.; Lassahn, Pamela L.; Martinson, Zoel R.; Sparks, Daniel T. & Schwieder, David H.
Partner: UNT Libraries Government Documents Department
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Appendix B. Insturmentation Transducer Calibration and Data Acquisition System Uncertaintites

Description: Report providing estimates of instrument calibration and data system acquisition errors as well as the equation for estimating 95% confidence levels for transducers and the surveillance system for the Power-Cooling-Mismatch (Test PCM-4).
Date: August 1979
Creator: Johnson, Roger L.; Lassahn, Pamela L.; Martinson, Zoel R.; Sparks, Daniel T. & Schwieder, David H.
Partner: UNT Libraries Government Documents Department
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Appendix D. Data Plots

Description: Report presenting data plots for selected parameters measured during Test PCM-4 of the Power-Cooling-Mismatch Test Series.
Date: August 1979
Creator: Johnson, Roger L.; Lassahn, Pamela L.; Martinson, Zoel R.; Sparks, Daniel T. & Schwieder, David H.
Partner: UNT Libraries Government Documents Department
open access

Experiment Data Report for Multirod Burst Test (MRBT) Bundle B-5

Description: "This report presents, in considerable detail, the experimental data for the B-5 test conducted by the Multirod Burst Test (MRBT) Program at Oak Ridge National Laboratory."
Date: August 1984
Creator: Chapman, R. H.; Crowley, J. L. & Longest, A. W.
Partner: UNT Libraries Government Documents Department
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NOZ-FLAW: A Finite Element Program for Direct Evaluation of Stress Intensity Factors for Pressure Vessel Nozzle-Corner Flaws

Description: From Abstract. "This report describes a linear elastic finite element computer program (NOZ-FLAW) which is used for the direct evaluation of mixed-mode stress intensity factors (K1, KII K111) along user-defined crack flaws at pressure-vessel nozzle corners." From Forward: "The work reported here was performed at the Oak Ridge National Laboratory and at the Georgia Institute of Technology under UCC-ND Subcontract No. 7565."
Date: March 1981
Creator: Atluri, Satya N.; Bass, B. R.; Bryson, J. W. & Kathiresan, K.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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COPS Model Estimates of LLEA Availability Near Selected Reactor Sites

Description: "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.
Partner: UNT Libraries Government Documents Department
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