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Acoustic Emission/Flaw Relationships for Inservice Monitoring of LWRs

Description: "The program concerning Acoustic Emission/Flaw Relationships for Inservice Monitoring of LWRs was entitled in FY76 with the objective of validating the application of acoustic emission (AE) to monitor nuclear reactor pressure-containing components during operation to detect cracking."
Date: October 1991
Creator: Hutton, P. H.; Kurtz, R. J.; Friesel, M. A.; Skorpik, J. R. & Dawson, J. F.
Partner: UNT Libraries Government Documents Department
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Appendix A: Additional Plots For Tests TC-1B, TC-1C, and TC-1D

Description: 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.
Partner: UNT Libraries Government Documents Department
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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
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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
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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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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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Loss-of-Coolant Accident Test Series -- Results of TC-1 Tests

Description: 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.
Partner: UNT Libraries Government Documents Department
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Identification of New Unresolved Safety Issues Relating to Nuclear Power Plants

Description: From abstract: As a result of review by the Nuclear Regulatory Commission (NRC) staff and extended collegial consultations and investigations within the NRC, the Commission has designated four new Unresolved Safety Issues (USIs). This report describes the process used to evaluate the large number of concerns and recommendations which resulted from the major investigations of the Three Mile Island-2 accident, as well as other events and investigations of the past year, and it identifies the four… more
Date: March 1981
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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Safety Evaluation Report Related to the Operation of San Onofre Nuclear Generating Station, Units 2 and 3

Description: From introduction: This report is a safety evaluation report on the application for operating licenses for the San Onofre Nuclear Generating Station, Units 2 and 3 (San Onofre 2 and 3 or the facility). This report was prepared by the United States Nuclear Regulatory Commission staff (the NRC staff or the staff), and summarizes the results of our radiological safety review of the facility.
Date: February 1981
Creator: U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.
Partner: UNT Libraries Government Documents Department
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Appendix A. Design and Test Conduct

Description: Report summarizing the design of Power Burst Facility (PBF) test rods, test train hardware, the individual rod assembly instrumentation, and test conduct.
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. Pretest Fuel Rod Charactization Data

Description: Report presenting the pretest fuel rod characterization data for four rods used in 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 C. Power Burst Facility Design and Capabilities

Description: Report providing a detailed description of the Power Burst Facility (PBF) design and capabilities, including an illustration of the axial cross section of the PBF in-pile tube.
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 D. Energy Deposition Measurements

Description: Report describing four different methods of measuring the total radially averaged fission energy deposited in PBF (Power Burst Facility) fuel rods, as well as a summary evaluation of each method.
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 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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Fault Tree Handbook

Description: Introduction: Since 1975, a short course entitled "System Safety and Reliability Analysis" has been presented to over 200 NRC personnel and contractors. The course has been taught jointly by David F. Haasl, Institute of System Sciences, Professor Norman H. Roberts, University of Washington, and members of the Probabilistic Analysis Staff, NRC, as part of a risk assessment training program sponsored by the Probabilistic Analysis Staff. This handbook has been developed not only to serve as text f… more
Date: January 1981
Creator: Roberts, N. H.; Vesely, W. E.; Haasl, D. F. & Goldberg, F. F.
Partner: UNT Libraries Government Documents Department
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FRAPCON-2 : A Computer Code for the Calculation of Steady State Thermal-Mechanical Behavior of Oxide Fuel Rods

Description: FRAPCON-2 is a FORTRAN IV computer code that calculates the steady state response of light Mater reactor fuel rods during long-term burnup. The code calculates the temperature, pressure, deformation, and tai lure histories of a fuel rod as functions of time-dependent fuel rod power and coolant boundary conditions. The phenomena modeled by the code include (a) heat conduction through the fuel and cladding, (b) cladding elastic and plastic deformation, (c) fuel-cladding mechanical interaction, (d… more
Date: January 1981
Creator: Berna, Gary A.; Bohn, Michael P.; Rausch, W. N.; Williford, R. E. & Lanning, D. D.
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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