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ROSA-IV/LSTF Program at JAERI for PWR Small-Break LOCA and Operational Transient Experiments

  • Mitsugu Tanaka
  • Kanji Tasaka
  • Yasuo Koizumi
  • Clifford P. Fineman
  • Masayoshi Shiba

Abstract

The Japan Atomic Energy Research Institute (JAERI) has initiated the Rig of Safety Assessment, Number 4 (ROSA-IV), program to study small-break loss-of-coolant accidents and operational transients. This paper describes the design features of LSTF and the results of the pre-analysis of LSTF tests.

Keywords

Steam Generator Secondary System Pressurize Water Reactor Japan Atomic Energy Research Institute Plenum Pressure 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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References

  1. 1.
    H. Nakamura, M. Tanaka, K. Tasaka, Y. Koizumi and H. Murata, “System Description for ROSA-IV Two-Phase Flow Test Facility (TPTF)”, JAERI-M 83-042 (1983).Google Scholar
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    M. Tanaka, K. Katada and K. Tasaka, “Pre-analysis of ROSA-IV LSTF for PWR Small-Break LOCA Test with RELAP5/MOD0-2.5% Cold Leg Break with HPI Failure”, JAERI-M 9676 (1981).Google Scholar
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    M. Tanaka, C. Fineman and K. Tasaka, “PORV Break Calculations for the ROSA-IV LSTF and the Reference PWR with RELAP5/MOD1 (Cycle 1)”, JAERI-M 83-067 (1983).Google Scholar
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Copyright information

© Springer Science+Business Media New York 1984

Authors and Affiliations

  • Mitsugu Tanaka
    • 1
  • Kanji Tasaka
    • 1
  • Yasuo Koizumi
    • 1
  • Clifford P. Fineman
    • 1
  • Masayoshi Shiba
    • 1
  1. 1.Japan Atomic Energy Research InstituteJapan

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