Simulation experiment of five percent small break loss-of-coolant accident of boiling water reactor.
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概要
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Five-percent small break tests have been conducted at the ROSA-III test facility with various emergency core cooling system (ECCS) actuation conditions. Break was assumed at the main recirculation pump inlet line. The ROSA-III facility simulated a BWR/6-251 by the volume scaling ratio of 1/424 and a 5% break area in a ROSA-III test means 5% of 1/424 of the BWR recirculation line pipe cross section. No dryout of fuel surface was observed in the tests with high pressure core spray system (HPCS) actuation irrespective of the conditions of the other ECCS. Without HPCS the whole core was uncovered to the steam environment ; however, the peak cladding temperature (PCT) was limited to 1, 022 K well below the present safety criteria of 1, 473 K. The results of the test with the highest PCT without HPCS actuation were analyzed by the RELAP4/Mod6 computer code. The calculated fuel surface temperatures agreed well with measured results in the blowdown phase. The calculated PCT was 930 K, 92 K below the measured PCT of 1, 022 K.
- 一般社団法人 日本原子力学会の論文
著者
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KUMAMARU Hiroshige
Japan Atomic Energy Research Institute
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ANODA Yoshinari
Japan Atomic Energy Research Institute
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TASAKA Kanji
Japan Atomic Energy Research Institute
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KOIZUMI Yasuo
Japan Atomic Energy Research Institute
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SHIBA Masayoshi
Japan Atomic Energy Research Institute
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