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Future plan of JET-ILW sample analysis as Broader Approach DEMO R&D and QST collaboration
https://repo.qst.go.jp/records/79436
https://repo.qst.go.jp/records/79436684d9f40-d30f-404c-b1f0-f58710e2723f
| Item type | 会議発表用資料 / Presentation(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2020-03-15 | |||||
| タイトル | ||||||
| タイトル | Future plan of JET-ILW sample analysis as Broader Approach DEMO R&D and QST collaboration | |||||
| タイトル | ||||||
| タイトル | Recent Progress of Plasma-Wall Interaction Studies in Large Fusion Devices | |||||
| 言語 | en | |||||
| 言語 | ||||||
| 言語 | jpn | |||||
| 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 |
朝倉, 伸幸
× 朝倉, 伸幸× 林, 巧× 谷川, 博康× 中道, 勝× Nobuyuki, Asakura× Takumi, Hayashi× Hiroyasu, Tanigawa× Masaru, Nakamichi |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | DEMO R&D activity is one of 4 activities in IFERC (QST Rokkasho): i.e. DEMO Design, DEMO R&D, Computer Simulation Center, ITER Remote Exp. Japan-EU joint team has conducted analyses from 2014. Analysis of JET ILW-1(2011-12) was completed. In 2018, new samples (ILW-3(2015-16): W-coated CFC & Dust, and ILW-1: Be first wall & W-lamellar), and in 2019 (ILW-3: Be first wall) were shipped from JET to Rokkasho. Analysis of ILW-3 samples is in progress. In 2020 spring, (ILW-3) W-lamellar samples will be shipped. 10 joint papers were published and presented in many major conferences. Systematic analysis results of JET-ILW samples will provide PWI database of PFC lifetime, Tritium retention and generation of tritiated and radioactive dust for ITER and DEMO. They will also contribute to database for safety analysis (T-release from PFCs and pollution by radioactive dust) in accident events. In future (2020 April - 2022 June): Research activity of the existing samples of ILW-3 continues. Complete T analysis of JET-ILW-3 tiles and dusts and summarize T inventory data. Additional research proposals (to 2024) of JA-EU collaboration are is in discussion. Evaluation Tritium removal from materials interim, and fuel cycle design: Investigation of Tritium inventory and removal using existing JET in-vessel components such as Inconel/SUS as well as PFCs used in JET DT (1990s). Sample analysis of new JET-ILW4? Relating to JET-DT? |
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| 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 | 第36回プラズマ・核融合学会 年会 | |||||
| 発表年月日 | ||||||
| 日付 | 2019-12-01 | |||||
| 日付タイプ | Issued | |||||
