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Simulation Studies of the Divertor Geometry and Plasma Parameters for 1.5 GW Fusion Power Demo Reactor
https://repo.qst.go.jp/records/66798
https://repo.qst.go.jp/records/66798f7b98945-0e62-410d-bb43-259673d5f6b7
| Item type | 会議発表用資料 / Presentation(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2018-05-01 | |||||
| タイトル | ||||||
| タイトル | Simulation Studies of the Divertor Geometry and Plasma Parameters for 1.5 GW Fusion Power Demo Reactor | |||||
| 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 |
Asakura, Nobuyuki
× Asakura, Nobuyuki× Hoshino, Kazuo× Tokunaga, Shinsuke× Shimizu, Katsuhiro× Uto, Hiroyasu× Kudo, Hironobu× Tobita, Kenji× Noriyashu, Ohno× 朝倉 伸幸× 星野 一生× 徳永 晋介× 清水 勝宏× 宇藤 裕康× 工藤 広信× 飛田 健次 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | Power handling in the main plasma and divertor has been investigated in steady-state Japan Demo concept of 1.5 GW-level fusion power and the major radiaus of Rp = 8.5m. System code (TPC) survey for the Ar impurity seeding suggested the designed <ne> of 6.6-7.2x1019m-3 was lower than that in ITER. 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 of frad = Prad/Pout = 0.8, as the first step to investigate appropriate design of the divertor size and geometry. Appropriate fuel and Ar puff rates were determined, where Praddiv was ~150MW (fraddiv ~ 0.6), (nAr/ne)SOL was decreased to 0.4-0.45% and nemid was increased to 2.3-2.4x1019m-3. In the outer divertor, the significant radiation peak was maintained in the divertor leg (near the separatrix) at 0.9-1.2 m below the X-point. At the outer target, partial detachment was produced near the strike-point (rdiv < 15 cm), and the peak qtarget at the attached region was ~5 MWm-2. At the inner divertor target, full detachment of ion flux was not produced due to Tediv = Tidiv ~1eV, and the peak qtarget was also ~5 MWm-2 mostly due to the surface-recombination. These results suggest a power exhaust scenario in Demo and the divertor design concept with long leg length, in which the peak-qtarget can be reduced less than 10 MWm-2 for both inner and outer divertor. | |||||
| 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 | 22nd International Conference on Plasma Surface Interactions in Controlled Fusion Devices | |||||
| 発表年月日 | ||||||
| 日付 | 2016-05-31 | |||||
| 日付タイプ | Issued | |||||
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Asakura, Nobuyuki, Hoshino, Kazuo, Tokunaga, Shinsuke, Shimizu, Katsuhiro, Uto, Hiroyasu, Kudo, Hironobu, Tobita, Kenji, Noriyashu, Ohno, 朝倉 伸幸, 星野 一生, 徳永 晋介, 清水 勝宏, 宇藤 裕康, 工藤 広信, 飛田 健次, n.d., Simulation Studies of the Divertor Geometry and Plasma Parameters for 1.5 GW Fusion Power Demo Reactor.
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