著者

尾本 彰 杉崎 利彦 長坂 秀雄

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.28, no.10, pp.950-956, 1986

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Many integral and separate effect experiments have been carried out cooperatively by the Japanese BWR utilities and vendors. Through these results, various counter-current-flow limitation phenomena occurring inside the BWR core, steam and mist cooling effect, multibundle effect etc. have been identified effectively to cool down the core during LOCA transients.<BR>Based on these findings and with other aids, SAFER code, which can better estimate the thermal-hydraulics of the BWR transient by the simple one-dimentional method, has been developed by the BWR vendors to replace with the existing SAFE-REFLOOD-CHASTE code system. <BR>The new code predicts the peak-cladding-temperature for the standard jet-pump BWR LOCA transients to be as high as 500600&deg;C, which is well below the current regulatory limitation. LOCA/ECCS constraints will be reduced for future BWR core managements and ECCS equipments surveillance etc. by the use of new code.