燃料デブリ臨界試験に向けたSTACY更新炉の核特性評価と安全設計の検討 (1) - 燃料デブリ臨界試験の概要と安全設計方針 (Evaluation of nuclear characteristics and safety design examination of modified STACY for critical experiments on fuel debris (1) - outline of critical experiments on fuel debris and safety design principle)

Submitted by Fukushima Nucl… on Thu, 12/03/2020 - 10:17

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Tohoku

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日本原子力研究開発機構

Media Creator Realname

日本原子力研究開発機構

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Japanese

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Sun, 03/30/2014 - 16:00

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Japanese Title

燃料デブリ臨界試験に向けたSTACY更新炉の核特性評価と安全設計の検討 (1) - 燃料デブリ臨界試験の概要と安全設計方針

Japanese Description

燃料デブリ臨界試験に向けたSTACY更新炉の核特性評価と安全設計の検討 (1) - 燃料デブリ臨界試験の概要と安全設計方針

English Title

Evaluation of nuclear characteristics and safety design examination of modified STACY for critical experiments on fuel debris (1) - outline of critical experiments on fuel debris and safety design principle

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https://f-archive.jaea.go.jp/dspace/handle/faa/41588

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https://f-archive.jaea.go.jp/dspace/handle/faa/41588