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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/72771
ac1a400b-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

WEKO 716830

Asakura, Nobuyuki

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Hoshino, Kazuo

× Hoshino, Kazuo

WEKO 716831

Hoshino, Kazuo

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Uto, Hiroyasu

× Uto, Hiroyasu

WEKO 716832

Uto, Hiroyasu

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Someya, Yoji

× Someya, Yoji

WEKO 716833

Someya, Yoji

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Tokunaga, Shinsuke

× Tokunaga, Shinsuke

WEKO 716834

Tokunaga, Shinsuke

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Suzuki, Satoshi

× Suzuki, Satoshi

WEKO 716835

Suzuki, Satoshi

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Ezato, Koichiro

× Ezato, Koichiro

WEKO 716836

Ezato, Koichiro

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Seki, Yoji

× Seki, Yoji

WEKO 716837

Seki, Yoji

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Kudo, Hironobu

× Kudo, Hironobu

WEKO 716838

Kudo, Hironobu

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Shimizu, Katsuhiro

× Shimizu, Katsuhiro

WEKO 716839

Shimizu, Katsuhiro

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Sakamoto, Yoshiteru

× Sakamoto, Yoshiteru

WEKO 716840

Sakamoto, Yoshiteru

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Hiwatari, Ryoji

× Hiwatari, Ryoji

WEKO 716841

Hiwatari, Ryoji

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Tobita, Kenji

× Tobita, Kenji

WEKO 716842

Tobita, Kenji

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Ohno, Noriyasu

× Ohno, Noriyasu

WEKO 716843

Ohno, Noriyasu

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Ueda, Yoshio

× Ueda, Yoshio

WEKO 716844

Ueda, Yoshio

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朝倉 伸幸

× 朝倉 伸幸

WEKO 716845

en 朝倉 伸幸

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星野 一生

× 星野 一生

WEKO 716846

en 星野 一生

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宇藤 裕康

× 宇藤 裕康

WEKO 716847

en 宇藤 裕康

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染谷 洋二

× 染谷 洋二

WEKO 716848

en 染谷 洋二

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徳永 晋介

× 徳永 晋介

WEKO 716849

en 徳永 晋介

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鈴木 哲

× 鈴木 哲

WEKO 716850

en 鈴木 哲

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江里 幸一郎

× 江里 幸一郎

WEKO 716851

en 江里 幸一郎

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関 洋治

× 関 洋治

WEKO 716852

en 関 洋治

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工藤 広信

× 工藤 広信

WEKO 716853

en 工藤 広信

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清水 勝宏

× 清水 勝宏

WEKO 716854

en 清水 勝宏

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坂本 宜照

× 坂本 宜照

WEKO 716855

en 坂本 宜照

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日渡 良爾

× 日渡 良爾

WEKO 716856

en 日渡 良爾

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飛田 健次

× 飛田 健次

WEKO 716857

en 飛田 健次

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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
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