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Examination of plasma-facing components in JET with the ITER-Like Wall: Strategy in studies and lessons for next-step devices
https://repo.qst.go.jp/records/66801
https://repo.qst.go.jp/records/668014a84f4a6-9914-411b-8f0d-aa176e52dc65
| Item type | 会議発表用資料 / Presentation(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2018-05-02 | |||||
| タイトル | ||||||
| タイトル | Examination of plasma-facing components in JET with the ITER-Like Wall: Strategy in studies and lessons for next-step devices | |||||
| 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 |
Rubel, M.
× Rubel, M.× Widdowson, A.× Grzonka, J.× Heinola, K.× Horton, L.× Jachmich, S.× Likonen, J.× Litaudon, X.× Ashikawa, N.× Asakura, Nobuyuki× 朝倉 伸幸 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | All plasma-facing components in ITER will be castellated to ensure thermo-mechanical stability. Grooves of the castellations may be considered as potential traps of fuel inventory and dust. JET with all-metal ITER-Like Wall (JET-ILW) is in operation since 2011: castellated berylllium limiters and tungsten divertor. The aims are to assess the purity of the castellation manufacture process, to develop techniques and procedures in sectioning of limiters exposed in JET, to determine morphology in the castellation following experimental campaign in JET, and to the impact of fuel inventory in the grooves on the total inventory in JET-ILW. Sectioning of tritium-contaminated beryllium limiters from JET-ILW has been performed for the first time. Only shallow deposition, 1-3 mm from the top of the groove, is found in the castellation. Fuel retention in the castellation is 10 times lower than on the plasma-facing surfaces of limiters. No dust has been identified in the castellation. The results clearly indicate that low carbon level in JET-ILW has significantly reduced fuel inventory. |
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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 | 18th International Conference on Fusion Reactor Materials (ICFRM-18) | |||||
| 発表年月日 | ||||||
| 日付 | 2017-11-06 | |||||
| 日付タイプ | Issued | |||||
