Assessment of SAFER03 code using ROSA-III break area spectrum tests on boiling water reactor loss-of-coolant accidents.

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概要

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• The SAFER03 computer code has a newly developed evaluation model for the analysis of various boiling water reactor (BWR) loss-of-coolant accidents (LOCAs). Analyses of the ROSA-IIIbreak area spectrum tests in a recirculation line were performed using the SAFER03 to assess the predictive capability of the code for a BWR LOCA. The ROSA-rn test facility at the Japan Atomic Energy Research Institute (JAERI) was constructed to simulate a LOCA in a BWR/6-251 plant with 848 fuel bundles and 24 jet pumps. This paper summarizes the assessment results of SAFER03 which predicted the system responses and key phenomena well and the conservative peak cladding temperature (PCT) for recirculation line break tests with different break areas.

• 一般社団法人 日本原子力学会の論文

著者

• TASAKA Kanji

  Department of Nuclear Safety Research, Japan Atomic Energy Research Instituter

関連論文

• Assessment of SAFER03 code using ROSA-III break area spectrum tests on boiling water reactor loss-of-coolant accidents.

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