Boiling water reactor loss of coolant tests. Single failure tests with ROSA-III.

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概要

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• The single failure tests with the ROSA-III were simulated BWR LOCA experiments by the scaled BWR test facility resulting from a 200% double-ended break at the recirculation pump suction line to evaluate the core cooling capability of a BWR ECCS under the single failure condition.<BR>The experimental results showed that the loss of LPCS and one LPCI resulted in the highest PCT of 870 K of the single failure series tests, yet a core cooling capability by the ECCS was maintained. The REALP4/Mod 6 code was used to evaluate the predictive capability of the LOCA analysis code. The calculated results showed that the RELAP4/Mod 6 code was able to predict occurrences and sequence of major events anticipated to occur during a BWR LOCA correctly. However it was found that the code still needs to be improved in a CCFL model to better describe thermohydraulic behavior in the core.<BR>The analyses presented in this paper are valuable for evaluating the adequacy and improving the predictive capability of analytical models developed to predict the system response of a BWR during a LOCA.

• 一般社団法人 日本原子力学会の論文

著者

• ABE Nobuaki

  Division of Reactor Safety, Japan Atomic Energy Research Institute

• SHIBA Masayoshi

  Division of Reactor Safety, Japan Atomic Energy Research Institute

• SODA Kunihisa

  Division of Reactor Safety, Japan Atomic Energy Research Institute

• TASAKA Kanji

  Division of Reactor Safety, Japan Atomic Energy Research Institute

関連論文

• Boiling water reactor loss of coolant tests. Single failure tests with ROSA-III.

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