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Estimation of Tritium Permeation Rate to Cooling Water in Fusion DEMO Condition
https://repo.qst.go.jp/records/48884
https://repo.qst.go.jp/records/4888444cfa693-14d4-45ea-ad6c-fea5eef7ed27
| Item type | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2018-05-08 | |||||
| タイトル | ||||||
| タイトル | Estimation of Tritium Permeation Rate to Cooling Water in Fusion DEMO Condition | |||||
| 言語 | ||||||
| 言語 | eng | |||||
| 資源タイプ | ||||||
| 資源タイプ識別子 | http://purl.org/coar/resource_type/c_6501 | |||||
| 資源タイプ | journal article | |||||
| アクセス権 | ||||||
| アクセス権 | metadata only access | |||||
| アクセス権URI | http://purl.org/coar/access_right/c_14cb | |||||
| 著者 |
片山, 一成
× 片山, 一成× 染谷, 洋二× 飛田, 健次× 中村, 博文× 谷川, 尚× 中村, 誠× 朝倉, 伸幸× 星野, 一生× 近田, 拓未× 波多野, 雄治× 深田, 智× 染谷 洋二× 飛田 健次× 中村 博文× 谷川 尚× 中村 誠× 朝倉 伸幸× 星野 一生 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | The approximate estimation of tritium permeation rate under the acceptable assumption from a safety point of view is surely useful to progress the design activities for a fusion DEMO reactor. Tritium permeation rates in the blanket and the divertor were estimated by the simplified evaluation model under the recent DEMO conditions in the water-cooled blanket with solid breeder as a first step. Plasma driven permeation rates in tungsten wall were calculated by applying Doyle & Brice model and gas driven permeation rates in F82H were calculated for hydrogen-tritium two component system. In the representative recent DEMO condition, the following tritium permeation rates were obtained, 1.8 g/day in the blanket first wall, 2.3 g/day in the blanket tritium breeding region and 1.6 g/day in the divertor. Total tritium permeation rate into the cooling water was estimated to be 5.7 g/day. | |||||
| 書誌情報 |
Fusion Science and Technology 巻 71, p. 261-267, 発行日 2018-05 |
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| DOI | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | 10.1080/15361055.2017.1288423 | |||||
