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タンク型SFRの大型原子炉容器に関する適用性の予備的検討,1; 耐震評価

Preliminary studies for applicability related to the large reactor vessel of pool-type SFR, 1; Seismic evaluation

内田 昌人*; 堂崎 浩二*; 鈴野 哲司*; 深沢 剛司*; 早船 浩樹; 加藤 篤志

Uchita, Masato*; Dozaki, Koji*; Suzuno, Tetsuji*; Fukasawa, Tsuyoshi*; Hayafune, Hiroki; Kato, Atsushi

タンク型のナトリウム冷却高速炉(SFR)の原子炉容器について、国内軽水炉サイト相当の地震条件を用いて耐震性の検討を行い、大型化に伴う原子炉容器の座屈に対する必要肉厚と水平免震装置から3次元免震装置に変更した場合の耐震性向上の程度を明らかにした。

Seismic evaluation on the reactor vessel of the pool type sodium-cooled reactor has been conducted using seismic conditions for domestic LWR sites. And parametric design survey when the reactor output is enlarged has also conducted showing available reactor vessel thickness with holizontal seismic isolation system and advanced design with three-dimensional seismic isolation system.

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