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Principle design and data of graphite components

黒鉛構造物の設計基準及び設計データ

石原 正博 ; 角田 淳弥 ; 柴田 大受 ; 伊与久 達夫; 奥 達雄*

Ishihara, Masahiro; Sumita, Junya; Shibata, Taiju; Iyoku, Tatsuo; Oku, Tatsuo*

HTTRは、炉心に六角柱ブロックを用いた黒鉛減速・ヘリウム冷却型高温ガス炉で、日本原子力研究所大洗研究所に建設された我が国初の高温ガス炉である。HTTRの炉内構造物は黒鉛によって形成される。黒鉛は脆性材料であり、脆性材料についての有用な設計基準は存在しないことから、原研では破壊挙動を考慮した設計基準を開発した。本報では、開発した黒鉛設計基準についての概要とその品質管理の概略について述べる。

The High Temperature Engineering Test Reactor (HTTR) constructed by Japan Atomic Energy Research Institute (JAERI) is a graphite-moderated and helium-gas-cooled reactor with prismatic fuel elements of hexagonal blocks. The reactor internal structures of the HTTR are mainly made up of graphite components. As well known, the graphite is a brittle material and there were no available design criteria for brittle materials. Therefore, JAERI had to develop the design criteria taking account of the brittle fracture behavior. In this paper, concept and key specification of the developed graphite design criteria is described, and also an outline of the quality control specified in the design criteria is mentioned.

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パーセンタイル:89.82

分野:Nuclear Science & Technology

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