111 Matching Results

Search Results

prev Results: 73 - 96 next
open access

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
open access

LOCA Analyses Annual Report: 1977

Description: Discussing sensitivity studies of the response surface developed for a seven-variable, sparsely-noded set of RELAP calculations.
Date: 1978
Creator: U.S. Nuclear Regulatory Commission. Division of Systems Safety.
Partner: UNT Libraries Government Documents Department
open access

LWR Pressure Vessel Irradiation Surveillance Dosimetry Quarterly Progress Report: October-December 1979

Description: This report was compiled at the Hanford Engineering Development Laboratory operated by Westinghouse Hanford Company, a subsidiary of Westinghouse Electric Corpoation, for the United States Department of Energy and the Nuclear Regulatory Commission, under DOE contract number DE-AC14-76FF02170 and NRC service request number TV-0176.
Date: December 1980
Creator: Guthrie, G. L. & McElroy, W. N.
Partner: UNT Libraries Government Documents Department
open access

Experiment Data Report for Multirod Burst Test (MRBT) Bundle B-6

Description: A report regarding experiment data for a multirod burst test, to investigate cladding deformation in the alpha-plus-beta-Ziracloy temperature range under light-water-reactor (LWR) loss-of-coolant accident (LOCA) conditions."
Date: June 11, 1984
Creator: Chapman, R. H.; Longest, A. W. & Crowley, J. L.
Partner: UNT Libraries Government Documents Department
open access

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
open access

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
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
open access

Appendix F. Cladding Surface Temperature Estimates

Description: Report discussing and comparing four techniques used for cladding temperatures achieved during Test RIA 1-1: metallorgraphic examination of cladding microstructures, computations based on isothermal oxidation kinetics, BUID5 computer code calculations, and weight gain calculations for metal-water reaction (p. 305)
Date: September 1980
Creator: Seiffert, Stephen L.; Martinson, Zoel R. & Fukuda, Steven K.
Partner: UNT Libraries Government Documents Department
open access

Appendix D. Metallographic Examination

Description: Report presenting the results of the metallographic examination for Rods 801-1, 801-2, 801-3, and 801-5 used to supplement the visual inspection and posttest description of the Test RIA 1-1 fuel rods. (p. 177)
Date: September 1980
Creator: Seiffert, Stephen L.; Martinson, Zoel R. & Fukuda, Steven K.
Partner: UNT Libraries Government Documents Department
open access

Appendix C. Fuel Rod Instrumentation

Description: Tables, text, and diagrams describing the design, instrumentation, and assembly of fuel rods uses in Test RIA 1-1.
Date: September 1980
Creator: Seiffert, Stephen L.; Martinson, Zoel R. & Fukuda, Steven K.
Partner: UNT Libraries Government Documents Department
open access

Appendix B. Pretest Fuel Rod Characterization

Description: "The pretest characterization of the four Test RIA 1-1 fuel rods and flow shrouds is presented in this appendix." (p. 147)
Date: September 1980
Creator: Seiffert, Stephen L.; Martinson, Zoel R. & Fukuda, Steven K.
Partner: UNT Libraries Government Documents Department
open access

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
open access

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
open access

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
open access

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
Back to Top of Screen