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電子書籍・電子雑誌船舶技術研究所報告
Volume number31 6
原子炉システムの信頼...

原子炉システムの信頼性解析手法GO-FLOWの開発研究

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原子炉システムの信頼性解析手法GO-FLOWの開発研究

Persistent ID (NDL)
info:ndljp/pid/10479711
Material type
記事
Author
松岡,猛ほか
Publisher
運輸省船舶技術研究所
Publication date
1994-12-28
Material Format
Digital
Journal name
船舶技術研究所報告 31(6)
Publication Page
p.271-345
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Notes on use

Note (General):

著者所属: 船舶技術研究所システム技術部著者所属: 船舶技術研究所原子力技術部

Detailed bibliographic record

Summary, etc.:

Probabilistic Safety Assessment (PSA) is important in the safely analysis of technological systems and processes, such as, nuclear plants, chemical an...

Bibliographic Record

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Digital

Material Type
記事
Author/Editor
松岡,猛
小林,道幸
Publication, Distribution, etc.
Publication Date
1994-12-28
Publication Date (W3CDTF)
1994-12-28
Alternative Title
Development of the GO-F10W Reliability Analysis Methodology for Nuclear Reactor System
Periodical title
船舶技術研究所報告
No. or year of volume/issue
31(6)
Volume
31(6)