Applicability of REFLA/TRAC Code to a Small-Break LOCA of PWR

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The applicability of the REFLA/TRAC code, which is one of best-estimate codes based on two-fluid model, was assessed for a typical small-break loss-of-coolant accident (SBLOCA) transient of PWR. The main assessment subject was to investigate whether the physical models in REFLA/TRAC can apply to the transient under SBLOCA condition (high pressure/low flow rate) or not. The applicability had been verified under low pressure/low flow rate condition during reflood phase in large-break LOCA transients of PWR. The assessment calculation was performed for Run SB-CL-05 (5% cold leg break SBLOCA test) in the ROSA-IV large-scale test facility. The REFLA/TRAC almost predicted the thermal-hydraulics in primary loops while the hydrau- lic models should be improved for regions at the pump side of loop seal and at the up-flow side of steam generator tube under CCFL condition. The core thermal-hydraulic models in REFLA/ TRAC give better prediction for core full-height differential pressure and the peak clad tem- perature (PCT) than those in original TRAC code. The PCT by the models in TRAC was lower about 100K than the measured one but the PCT by those in REFLA/TRAC was lower only about 40K.

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  • Journal of nuclear science and technology  

    Journal of nuclear science and technology 32(3), 245-256, 1995-03-25 

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10002072264
  • 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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