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Development of a plant system concept for a water-cooled fusion DEMO plant
https://repo.qst.go.jp/records/72569
https://repo.qst.go.jp/records/72569e4d89620-31c9-4ae2-8403-9eaf50868eea
| Item type | 会議発表用資料 / Presentation(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2017-12-07 | |||||
| タイトル | ||||||
| タイトル | Development of a plant system concept for a water-cooled fusion DEMO plant | |||||
| 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_c94f | |||||
| 資源タイプ | conference object | |||||
| 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 |
Miyoshi, Yuuya
× Miyoshi, Yuuya× Aoki, Akira× Hiwatari, Ryoji× Sakamoto, Yoshiteru× Tobita, Kenji× 三善 悠矢× 青木 晃× 日渡 良爾× 坂本 宜照× 飛田 健次 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | The primary cooling water systems (CWS) of the blanket and the divertor is expected to have several amount of tritium because of permeation from the core plasma. In this research, the required performance of DEMO tritium removal facility to control the primary tritium concentration has been calculated and it is shown that existing devices can be applied to DEMO. The primary tritium is also expected to permeate the pipes to the secondary, thirdly CWS and finally, discharged into seawater. The evaluation of discharged tritium rate into seawater has been done. Because of tritium transport model from water to water is not well known, gas to gas calculation model is used. The results show that a heat exchanger decreases the tritium permeation rate by 1 order of magnitude, and H2 addition to the upstream cooling water also decreases the tritium permeation rate by 3 orders of magnitude. | |||||
| 会議概要（会議名, 開催地, 会期, 主催者等） | ||||||
| 内容記述タイプ | Other | |||||
| 内容記述 | 13th International Symposium on Fusion Nuclear Technology | |||||
| 発表年月日 | ||||||
| 日付 | 2017-09-28 | |||||
| 日付タイプ | Issued | |||||
