Assessment of current safety evaluation analysis on reflood behavior during PWR-LOCA by using CCTF data.
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概要
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This paper describes an assessment result on conservatism of current safety analysis concerning reflood behavior during a LOCA in a PWR by using the experimental data with cylindrical core test facility (CCTF) performed at Japan Atomic Energy Research Institute (JAERI). WREM code is selected for a representative of current safety analyses.<BR>The predicted peak clad temperature with the WREM code was higher than the data, and it was confirmed that the WREM code had the overall conservatism against CCTF data.<BR>The WREM code predicted the reasonable core boundary conditions and it was found that the conservatism of the code came mainly from the calculations on the incore thermal hydraulics and clad temperature. In addition, it was found that the conservatism of the WREM code against the CCTF data could be attributed to the neglection of horizontal fluid mixing between subchannels, the neglection of the heat transfer enhancement due to the radial core power profile, and the usage of the heat transfer correlations conservative against CCTF data.
- 一般社団法人 日本原子力学会の論文
著者
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OKUBO Tsutomu
Japan Atomic Energy Agency
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Sugimoto Jun
Japan Atomic Energy Research Institute
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Akimoto Hajime
Japan Atomic Energy Agency
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MURAO Yoshio
Japan Atomic Energy Research Institute
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Iguchi Tadashi
Japan Atomic Energy Research Institute Department Of Reactor Safety Research
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HOJO Tsuneyuki
Japan Atomic Energy Research Institute
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