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Safety studies of plasma-wall events with AINA code for Japanese DEMO
https://repo.qst.go.jp/records/47844
https://repo.qst.go.jp/records/47844240210ad-4828-4545-8c40-b12417cc7a9e
| アイテムタイプ | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2017-04-27 | |||||
| タイトル | ||||||
| タイトル | Safety studies of plasma-wall events with AINA code for Japanese DEMO | |||||
| 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 |
Rivas, J.C.
× Rivas, J.C.× 中村, 誠× 染谷, 洋二× 星野, 一生× 朝倉, 伸幸× 高瀬治彦× 三善, 悠矢× 宇藤, 裕康× 飛田, 健次× Dies, J.× de, Blas A.× Riego, A.× Fabbiri, M.× 中村 誠× 染谷 洋二× 星野 一生× 朝倉 伸幸× 三善 悠矢× 宇藤 裕康× 飛田 健次 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | In this contribution, the work done in AINA code during 2014 and 2015 at IFERC is presented. The main motivation of this work was to adapt the code and to perform safety studies for a Japanese DEMO design. Related to AINA code, the work has supposed major changes in plasma models. Significant is the addition of an integrated SOL-pedestal model that allows the estimation of heat loads at divertor. Also, a thermal model for a WCPB (water cooled pebble bed) breeding blanket has been developed based in parametric input data from neutronics calculations. Related to safety studies, a major breakthrough in the study of LOPC (loss of plasma control) transients has been the use of an optimization method to determine the most severe transients in terms of the shortest melting times. \nThe results of the safety study show that LOPC transients are not likely to be severe for breeding blanket, but for the case of divertor can induce severe melting. For ex-vessel LOCA (loss of coolant accident) analysis, it is severe for both blanket and divertor, but in the first case the transient time until melting is nearly two orders of magnitude higher. The results point out that the recovery time for plasma control system should be at least one order of magnitude lower than confinement time to avoid melting of divertor targets. |
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| 書誌情報 |
Fusion Engineering and Design 巻 109/111, p. 1653-1657, 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.2015.10.037 | |||||
