WEKO3
アイテム
Physics and Engineering Design Studies on Power Exhaust and Divertor for a 1.5 GW Fusion Power DEMO
https://repo.qst.go.jp/records/72771
https://repo.qst.go.jp/records/72771ac1a400b-72d3-4003-9f38-3e9b401b8f97
| 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 | Physics and Engineering Design Studies on Power Exhaust and Divertor for a 1.5 GW 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_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× Uto, Hiroyasu× Someya, Yoji× Tokunaga, Shinsuke× Suzuki, Satoshi× Ezato, Koichiro× Seki, Yoji× Kudo, Hironobu× Shimizu, Katsuhiro× Sakamoto, Yoshiteru× Hiwatari, Ryoji× Tobita, Kenji× Ohno, Noriyasu× Ueda, Yoshio× 朝倉 伸幸× 星野 一生× 宇藤 裕康× 染谷 洋二× 徳永 晋介× 鈴木 哲× 江里 幸一郎× 関 洋治× 工藤 広信× 清水 勝宏× 坂本 宜照× 日渡 良爾× 飛田 健次 |
|||||
| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | Power handling and the divertor design has been investigated in steady-state Japan DEMO concept of 1.5 GW-level fusion power (Pfus) and the major radius of Rp = 8.5m. System code survey suggested to increase the plasma elongation (k95) from 1.65 to 1.75, loading to increasing Ip and ne, in order to obtain Pfus larger than 1.5 GW in the impurity seeding scenario, where the radiation power in the main plasma (Pradmain) is 180 MW (Pradmain/Pheat = 0.41, where Pheat= 430 MW), impurity concentration in the main plasma, (nAr/ne)core, of 0.5-0.75%. Design of the divertor size and geometry for the power exhaust parameter (Psep/Rp) of 29 MWm-1 was investigated by the divertor simulation (SONIC), where the outer leg lengths of 1.6 and 2.0 m were compared for a high radiation fraction (Praddiv/Pheat = 0.44). For the shorter leg divertor, the peak qtarget at the attached region (Tediv ~20 eV, Tidiv ~30eV) in the partial detached divertor was ~5 MWm-2 and it was also ~5 MWm-2 mostly due to the surface-recombination in the inner divertor (Tediv = Tidiv ~1eV). The longer leg divertor was preferable to reduce qtarget since the partial detachment extended to the outer flux surface, while the size of the vessel and TFC become larger. It was found that Cu-ally (CuCrZr) cooling pipe is applicable as the heat sink to handle the high heat flux near the strike-point, where displacements per atom (DPA) rate on Cu-alloy was estimated to be 1-2 per year from neutronics calculation. Coolant rooting for Cu-alloy and RAFM steel pipes and the flow velocities were determined to handle the peak qtarget of 10 MWm-2 level and the total thermal and nuclear heat removal of 300 MW and 118 MW, respectively. Heat transport and thermomechanical analyses of the W-monoblock and Cu-alloy pipes were performed. The maximum temperature of the Cu-ally pipe was 331C at the side surface. Heat flux of 16 MWm-2 is distributed in the major part of the interlayer side, while the maximum heat flux of 25 MWm-2 was localized near the poloidal side surface of the monoblock, which was acceptable level. The physics and engineering results were consistent for an integrated DEMO divertor design, which can handle the peak qtaret of 10 MWm-2 level. The integrated design of the two different water-cooling heat sinks for the divertor with Ldiv = 1.6m was shown. | |||||
| 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 | 26th IAEA Fusion Energy Conference | |||||
| 発表年月日 | ||||||
| 日付 | 2016-10-21 | |||||
| 日付タイプ | Issued | |||||
