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Studies of Power Exhaust and Divertor Design for a 1.5 GW-level Fusion Power DEMO
https://repo.qst.go.jp/records/48656
https://repo.qst.go.jp/records/486562995aac8-70ba-4c96-a60e-a751b1fb45cc
| Item type | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2018-03-28 | |||||
| タイトル | ||||||
| タイトル | Studies of Power Exhaust and Divertor Design for a 1.5 GW-level Fusion Power 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 |
朝倉, 伸幸
× 朝倉, 伸幸× 星野, 一生× 鈴木, 哲× 徳永, 晋介× 染谷, 洋二× 宇藤, 裕康× 工藤, 広信× 坂本, 宜照× 日渡, 良爾× 飛田, 健次× 清水, 勝宏× 江里, 幸一郎× 大野, 哲靖× 上田, 良夫× 朝倉 伸幸× 星野 一生× 鈴木 哲× 徳永 晋介× 染谷 洋二× 宇藤 裕康× 工藤 広信× 坂本 宜照× 日渡 良爾× 飛田 健次 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | Power exhaust to the divertor and the conceptual design have been investigated for a steady-state DEMO in Japan with 1.5 GW-level fusion power and the major radius of 8.5 m, where the plasma parameters were revised appropriate for the impurity seeding scenario. A system code survey for the Ar impurity seeding suggested the volume-averaged density, impurity concentration and exhaust power from the main plasma of Psep = 205-285 MW. The divertor plasma simulation (SONIC) was performed in the divertor leg length of 1.6 m with the fixed exhaust power to the edge of Pout = 250MW and the total radiation fraction at the edge, SOL and divertor (Prad/Pout = 0.8), as a first step to investigate appropriate design of the divertor size and geometry. At the outer target, partial detachment was produced near the strike-point, and the peak heat load (qtarget) at the attached region was reduced to ~5 MWm-2 with appropriate fuel and impurity puff rates. At the inner divertor target, full detachment of ion flux was produced and the peak qtarget was less than 10 MWm-2 mostly due to the surface-recombination. These results showed a power exhaust scenario and the divertor design concept. An integrated design of the water-cooling heat sink for the long leg divertor was proposed. Cu-ally (CuCrZr) cooling pipe was applicable as the heat sink to handle the high heat flux near the strike-point, where displacements per atom rate was estimated to be 0.5-1.5 per year by neutronics calculation. An arrangement of the coolant rooting for Cu-alloy and Reduced Activation Ferritic Martensitic (RAFM) steel (F82H) pipes in a divertor cassette was investigated, and the heat transport analysis of the W-monoblock and Cu-alloy pipe under the peak qtarget of 10 MWm-2 and nuclear heating was performed. The maximum temperatures on the W-surface and Cu-alloy pipe were 1021 and 331C. Heat flux of 16 MWm-2 was distributed in the major part of the coolant pipe. These results were acceptable for the plasma facing and structural materials. | |||||
| 書誌情報 |
Nuclear Fusion 巻 57, 号 12, p. 126050-1-126050-12, 発行日 2017-10 |
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| 出版者 | ||||||
| 出版者 | IOP Publishing | |||||
| DOI | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | 10.1088/1741-4326/aa867a | |||||
| 関連サイト | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | https://doi.org/10.1088/1741-4326/aa867a | |||||
| 関連名称 | https://doi.org/10.1088/1741-4326/aa867a | |||||
