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Compilation, Assessment and Expansion of the Strong Earthquake Ground Motion Data Base: Seismic Margins Research Program (SSMRP)

Description: A catalog had been prepared which contains information for world-wide, ground-motion accelerograms, the accelerogaph sites where these records were obtained, and the seismological parameters of the causative earthquakes.
Date: September 1980
Creator: Crouse, C. B.; Hileman, J. A.; Turner, B. E. & Martin, G. R.
Partner: UNT Libraries Government Documents Department

Fuel Rod Behavior During Tests PCM 8-1 RS, CHF Scoping, and PCM 8-1 RF

Description: This report presents the results of the first three power-cooling-mismatch tests - Tests 8-1 RS CHF Scoping, and 8-1 RF - performed in the PCM Test Series.
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

Test PCM-5 Fuel Rod Materials Behavior

Description: 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.
Partner: UNT Libraries Government Documents Department

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) fission gas release, (e} fuel rod internal gas pressure, (f) heat transfer between fuel and cladding, (g) cladding oxidation, and (h) heat transfer from cladding to coolant. The code contains necessary material properties, water properties, and heat transfer correlations. FRAPCON-2 is programmed for use on the CDC Cyber 175 and 176 computers. The FRAPCON-2 code Is designed to generate initial conditions for transient fuel rod analysis by either the FRAP-T6 computer code or the thermal-hydraulic code, RELAP4/MOD7 Version 2.
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

Power Plant Staffing

Description: 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.
Partner: UNT Libraries Government Documents Department

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

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

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

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

Nuclear Power Plant Fire Protection

Description: 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.
Partner: UNT Libraries Government Documents Department

SABRES II: Code Description and Users Manual

Description: 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
Partner: UNT Libraries Government Documents Department

Fuel Rod Material Behavior During Test PCM-1

Description: This report presents the analysis of the fuel rod materials behavior based on the postirradiation examination of the Test PCM-1 fuel rod from the Power-Cooling-Mismatch Test Series.
Date: June 1979
Creator: Cook, Beverly A.
Partner: UNT Libraries Government Documents Department

Fuel Rod Behavior During Test PCM-4

Description: This report presents and discusses the results from 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