Verification of FEMAXI-7 code by using irradiation test in Halden reactor for He-pressurization effect on FGR of BWR fuels under power transient
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概要
- 論文の詳細を見る
- 2012-05-01
著者
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Hanawa Satoshi
Nuclear Safety Research Center Japan Atomic Energy Agency
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OHGIYANAGI Jin
Nuclear Safety Research Center, Japan Atomic Energy Agency
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SUZUKI Motoe
Nuclear Safety Research Center, Japan Atomic Energy Agency
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Ohgiyanagi Jin
Nuclear Safety Research Center Japan Atomic Energy Agency
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Suzuki Motoe
Nuclear Safety Research Center Japan Atomic Energy Agency
関連論文
- Verification of FEMAXI-7 code by using irradiation test in Halden reactor for He-pressurization effect on FGR of BWR fuels under power transient
- A Water Radiolysis Code for the Irradiation Loop System