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Radwaste management aspects of the test blanket systems in ITER
https://repo.qst.go.jp/records/47825
https://repo.qst.go.jp/records/478254b9f873a-a06e-41b8-9832-51989d7b4abf
Item type | 学術雑誌論文 / Journal Article(1) | |||||
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公開日 | 2017-04-26 | |||||
タイトル | ||||||
タイトル | Radwaste management aspects of the test blanket systems in ITER | |||||
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 |
van, der Laan J.G.
× van, der Laan J.G.× Canas, D.× Chaudhari, V.× Iseli, M.× 河村, 繕範× Lee, D.W.× Petit, P.× Pitcher, C.S.× Torcy, D.× Ugolini, D.× Zhang, H.× 河村 繕範 |
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抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | Test Blanket Systems (TBS) will be operated in ITER in order to prepare the next steps towards fusion power generation. After the initial operation in H/He plasmas, the introduction of D and T in ITER will mark the transition to nuclear operation. The significant fusion neutron production will give rise to nuclear heating and tritium breeding in the in-vessel part of the TBS. The management of the activated and tritiated structures of the TBS from operation in ITER is described. The TBS specific features like tritium breeding and power conversion at elevated temperatures, and the use of novel materials require a dedicated approach, which could be different to that needed for the other ITER equipment. | |||||
書誌情報 |
Fusion Engineering and Design 巻 109/111, p. 222-226, 発行日 2016-11 |
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出版者 | ||||||
出版者 | Elsevier | |||||
DOI | ||||||
識別子タイプ | DOI | |||||
関連識別子 | 10.1016/j.fusengdes.2016.03.022 |