Nuclear Engineering and Technology

  • 제56권3호
  • /
  • Pages.886-892
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  • 2024
  • /
  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Evaluation of temperatures and flow areas of the Phebus Test FPT0

  • Koji Nishida (Institute of Nuclear Safety System, Incorporated) ;
  • Naoki Sano (Institute of Nuclear Safety System, Incorporated) ;
  • Seitaro Sakurai (Institute of Nuclear Safety System, Incorporated) ;
  • Michio Murase (Institute of Nuclear Safety System, Incorporated)
  • 투고 : 2023.06.29
  • 심사 : 2023.10.31
  • 발행 : 2024.03.25
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초록

The cladding temperatures and axial mass distribution computed by MAAP5 were compared with their measured values in the test bundle of the Phebus Test FPT0. The computed cladding temperatures were in good agreed with the measured values in the pre-transient phase. In the transient heat-up phase, the computed temperatures were overestimated by the Baker-Just correlation in MAAP5, but the computed temperatures could simulate the subsequently measured values. The computed mass distribution in the axial direction was in qualitative agreement with the measured one for post-test fuel damage observations. The calculated flow areas of inner and outer regions in the test bundle were compared with the photographic observations. MAAP5 computed them at the height of 0.2 m where the molten pool formed was in qualitative agreement with the photographic observations. It was found that the remaining steam flow paths might be caused by the gas-liquid two-phase flow counter-current flow limitation.

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참고문헌

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