Experimental Study on Difference in Reflood Core Heat Transfer among CCTF, FLECHT-SET and Predicted with FLECHT Correlation.
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概要
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It has been reported that the core heat transfer coefficients measured in the CCTF tests, which were conducted under the conditions expected to appear during the reflooding period in a PWR, can not be predicted well with the FLECHT correlation, which has been used in the safety evaluation. In order to investigate the reason for this, a CCTF test was conducted under the typical FLECHT-SET experimental conditions. Investigating results from both tests, the following has been clarified: <BR>The FLECHT correlation can not describe the heat transfer for the reflooding situations with the initial Accumulator injection period, which is expected to appear in a PWR, and gives much lower values than the measured. The core heat transfer in the FLECHT-SET is similar to that in the CCTF, and they are well predicted with the Murao-Sugimoto correlation. When there is some core radial power distribution, which strongly affects the heat transfer in a large scale core, the heat transfer coefficients in the CCTF can be well predicted with taking account of this effect in addition to the Murao-Sugimoto correlation.
- 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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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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IGUCHI Tadashi
Japan Atomic Energy Research Institute
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