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RELAP5 Analyses of Overcooling Transients in a Pressurized Water Reactor

  • M. A. Bolander
  • C. D. Fletcher
  • D. M. Ogden
  • B. D. Stitt
  • M. E. Waterman

Abstract

In support of the Pressurized Thermal Shock Integration Study sponsored by the United States Nuclear Regulatory Commission, the Idaho National Engineering Laboratory has performed analyses of overcooling transients using the RELAP5/MOD1.5 computer code. These analyses were performed for Oconee Plants 1 and 3, which are pressurized water reactors of Babcock and Wilcox lowered-loop design. Results of the RELAP5 analyses are presented, including a comparison with plant data. The capabilities and limitations of the RELAP5/MOD1.5 computer code in analyzing integral plant transients are examined. These analyses require detailed thermal-hydraulic and control system computer models.

Keywords

Steam Generator Pressurize Water Reactor Nuclear Regulatory Commission Integrate Control System Idaho National Engineer Laboratory 
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References

  1. 1.
    M. A. Bolander, C. D. Fletcher, B. D. Stitt, M. E. Waterman, RELAP5 Analysis of Oconee-1 PWR Transients for Pressurized Thermal Shock Integration Study (Proprietary), EG&G Idaho Report EGG-NTAP-6190, March 1983.Google Scholar
  2. 2.
    C. D. Fletcher, M. A. Bolander, B. D. Stitt, M. E. Waterman, RELAP5 Thermal-Hydraulic Analysis of Pressurized Thermal Shock Sequences for the Oconee-1 Pressurized Water Reactor, EG&G Idaho Report EGG-NSMD-6343, July 1983.Google Scholar
  3. 3.
    V. H. Ransom, R. O. Wagner, J. A. Trapp, K. E. Carlson, D. M. Riser, H. H. Kuo, H. Chow, R. A. Nelson, S. W. James, RELAP5/MOD1 Code Manual, Volumes 1 and 2, EG&G Idaho Report NUREG/CR-1826, EGG-2070, November 1980.Google Scholar

Copyright information

© Springer Science+Business Media New York 1984

Authors and Affiliations

  • M. A. Bolander
    • 1
  • C. D. Fletcher
    • 1
  • D. M. Ogden
    • 1
  • B. D. Stitt
    • 1
  • M. E. Waterman
    • 1
  1. 1.Idaho National Engineering LaboratoryEG&G Idaho, Inc.Idaho FallsUSA

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