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J-GLOBAL ID：201802269584042053   Reference number：18A2001476

Evaluation of tritium leakage rate into seawater in fusion DEMO cooling water system

核融合DEMO冷却水システムにおける海水へのトリチウム漏れ率の評価【JST・京大機械翻訳】

Author (5)： Miyoshi Yuya (National Institutes for Quantum and Radiological Science and Technology, 2-166 Oaza Obuchi Aza Omotedate Rokkasyo, Aomori, Japan) ,  Aoki Akira (National Institutes for Quantum and Radiological Science and Technology, 2-166 Oaza Obuchi Aza Omotedate Rokkasyo, Aomori, Japan) ,  Hiwatari Ryoji (National Institutes for Quantum and Radiological Science and Technology, 2-166 Oaza Obuchi Aza Omotedate Rokkasyo, Aomori, Japan) ,  Sakamoto Yoshiteru (National Institutes for Quantum and Radiological Science and Technology, 2-166 Oaza Obuchi Aza Omotedate Rokkasyo, Aomori, Japan) ,  Tobita Kenji (National Institutes for Quantum and Radiological Science and Technology, 2-166 Oaza Obuchi Aza Omotedate Rokkasyo, Aomori, Japan)
Material： Fusion Engineering and Design  (Fusion Eng Des)
Volume： 136  Issue： PB  Page： 1577-1580  Publication year： 2018 
JST Material Number： T0497A  ISSN： 0920-3796  CODEN： FEDEEE  Document type： Article
Article type： 原著論文  Country of issue： Netherlands (NLD)  Language： ENGLISH (EN)

Abstract/Point： The primary cooling water syst...

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Thesaurus term： computation model ,  Nuclear Fusion ,  plasma ,  *sea water ,  turbine ,  blanket ,  *cooling water ,  plant (industrial) ,  system design ,  *tritium ,  heat exchanger ,  divertor ,  tritium permeation ,  transport model
Semi thesaurus term： 一次冷却水 , 【Automatic Indexing@JST】

Author keywords (4)： Plant system design ,  DEMO design ,  Cooling water system ,  Tritium permeation

JST classification (1)： Fusion devices  (BJ02083Z)

Terms in the title (7)： 核融合 ,  DEMO ,  冷却水 ,  海水 ,  トリチウム ,  漏れ率 ,  評価