ROSA/AP600 Testing : Facility Modifications and Initial Test Results

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The Japan Atomic Energy Research Institute (JAERI) and the United States Nuclear Regulatory Commission (USNRC) are jointly conducting confirmatory, integral testing on the Westinghouse AP600 reactor transient responses by using the ROSA-V Large Scale Test Facility of JAERI. This facility, built originally to simulate conventional 4-loop pressurized water reactors (PWRs), has been modified by adding components specific to the AP600 design. The modified LSTF now provides a full-pressure, full-height, 1/30.5 volumetrically-scaled simulation of AP600. Five loss-of-coolant accident (LOCA) experiments were performed by August 1994, simulating transients initiated by cold leg breaks, a Pressure Balance Line (PBL) break, and inadvertently open Automatic Depressurization System (ADS) valves. These experiments indicated adequate core cooling and decay heat removal performance of the AP600 passive safety components.

収録刊行物

  • Journal of nuclear science and technology

    Journal of nuclear science and technology 33(3), p.259-265, 1996-03-25

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10002074473
  • NII書誌ID(NCID)
    AA00703720
  • 本文言語コード
    ENG
  • 資料種別
    ART
  • ISSN
    00223131
  • データ提供元
    CJP書誌  CJP引用  J-STAGE 
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