著者

白井 孝治 伊藤 千浩 加藤 安久 服部 清一 三枝 利有 大沼 博志

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.37, no.5, pp.430-441, 1995-05-30 (Released:2010-01-08)

参考文献数

13

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Cask-storage is the best method for storing spent fuels at a reactor site. It is necessary to confirm the integrity of a cask subjected to impact load caused by cask mishandling drop accident because it is one of the technical issues to be considered in the safety analysis for cask and storage house. In this paper, an evaluation method of the dynamic interaction between cask and floor of the Storage facility Subjected to impact load is proposed. Firstly, the cask drop tests onto the reinforced concrete slab representing floor of the storage facility were conducted. Test results showed that the structural integrity of the cask was maintained even under impact load due to free drop caused by mishandling of cask. Secondly, drop analysis was performed using a finite element method analysis code considering concrete model developed at our laboratory, and compared with the experimental results. As a result, the applicability of this code for drop impact analysis of the cask was confirmed.