MCNPコードの金属キャスク貯蔵方式中間貯蔵施設線量評価への適用
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- Material Type
- 記事
- Author/Editor
- 小佐古 敏荘飯本 武志石川 智之 他
- Alternative Title
- Application of dose evaluation of the MCNP code for interim spent fuel cask storage facility
- Periodical title
- 日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan
- No. or year of volume/issue
- 6(2) (通号 22) 2007.6
- Volume
- 6
- Issue
- 2
- Sequential issue number
- 22