Analysis of BWR pressure suppression pool dynamics

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Description

The design basis loss of coolant accident (LOCA) for light water nuclear reactors postulates a major break in a coolant line. Both the response of the reactor vessel and its mechanical system as well as the response of the pressure suppression containment system exterior to the pressure vessel are of primary interest following such an event. The ability to determine system response and the suitability of particular mechanical and structural design features in both cases is predicted on the completeness with which the dynamic environment created in the various compartments is treated. In January of 1976, the Lawrence Livermore Laboratory … continued below

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24 pages

Creation Information

McCauley, E. W.; Martin, R. W. & Sutton, S. B. August 30, 1976.

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  • Lawrence Livermore Laboratory
    Publisher Info: California Univ., Livermore (USA). Lawrence Livermore Lab.
    Place of Publication: Livermore, California

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Description

The design basis loss of coolant accident (LOCA) for light water nuclear reactors postulates a major break in a coolant line. Both the response of the reactor vessel and its mechanical system as well as the response of the pressure suppression containment system exterior to the pressure vessel are of primary interest following such an event. The ability to determine system response and the suitability of particular mechanical and structural design features in both cases is predicted on the completeness with which the dynamic environment created in the various compartments is treated. In January of 1976, the Lawrence Livermore Laboratory (LLL) began a program for the NRC (RSR) to provide a sample problem solution activity which treats by numerical analysis the air-steam-water system flow implied by a LOCA. As a basis and focal point for modeling, the program addressed itself to the pressure suppression pool dynamics representative of the Mark I BWR. Program activities to date are described.

Physical Description

24 pages

Notes

Dep. NTIS

Source

  • 4. water reactor safety research information meeting, Washington, DC, USA, 27 Sep 1976

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  • Report No.: UCRL-78694
  • Report No.: CONF-760954-2
  • Grant Number: W-7405-ENG-48
  • Office of Scientific & Technical Information Report Number: 7325289
  • Archival Resource Key: ark:/67531/metadc1448153

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • August 30, 1976

Added to The UNT Digital Library

  • Feb. 10, 2019, 8:45 p.m.

Description Last Updated

  • Jan. 19, 2021, 10:29 p.m.

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McCauley, E. W.; Martin, R. W. & Sutton, S. B. Analysis of BWR pressure suppression pool dynamics, article, August 30, 1976; Livermore, California. (https://digital.library.unt.edu/ark:/67531/metadc1448153/: accessed July 17, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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