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Progress of divertor study on DEMO design
https://repo.qst.go.jp/records/47992
https://repo.qst.go.jp/records/47992227ae4d5-e995-468d-8af9-b3570822f485
| Item type | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2017-05-30 | |||||
| タイトル | ||||||
| タイトル | Progress of divertor study on DEMO design | |||||
| 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 |
星野, 一生
× 星野, 一生× 朝倉, 伸幸× 徳永, 晋介× 清水, 勝宏× 本間, 裕貴× 染谷, 洋二× 宇藤, 裕康× 坂本, 宜照× 飛田, 健次× Joint, Special Design Team for fusion DEMO The× 星野 一生× 朝倉 伸幸× 徳永 晋介× 清水 勝宏× 本間 裕貴× 染谷 洋二× 宇藤 裕康× 坂本 宜照× 飛田 健次 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | Recent progress of the physics and engineering design study for the 8 m-sized DEMO is reported. Parametric study for the divertor of the compact DEMO (a machine size ∼ 5.5 m) by using the SONIC code shows that the target heat load less than 10 MW/m^2 around the fusion power of ∼1.5 GW and the impurity radiation fraction of more than 80 %. In the 8 m sized DEMO with these parameters, the partial detachment is obtained at the outer divertor, even in the low SOL density, due to the large impurity radiation in the SOL and divertor region. The SONIC simulation shows the peak of the target heat load is 7 MW/m^2. However, the peak of the ion temperature at the target is considerably high, which causes significant erosion of the target. The divertor power handling and decrease in the ion temperature have to be proceeded by the scenario development of the divertor plasma operation as well as the core plasma design and the engineering design. In the engineering study side, the tungsten monoblock target with the water cooling and the Cu-alloy cooling tube is designed. The MCNP-5 neutronics analysis shows applicability of the Cu-alloy cooling tube for the divertor unit on the high heat flux region. Also the divertor cassette with a heat removability of peak heat load of 10 MW/m2 is studied. The heat transport analysis shows the maximum temperature of 1021 °C at the tungsten surface and 331 °C at the Cu-alloy pipe, which are acceptable level for mechanical toughness and thermal fatigue. | |||||
| 書誌情報 |
Plasma and Fusion Research 巻 12, p. 1405023, 発行日 2017-05 |
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| 出版者 | ||||||
| 出版者 | The Japan Society of Plasma Science and Nuclear Fusion Research | |||||
| ISSN | ||||||
| 収録物識別子タイプ | ISSN | |||||
| 収録物識別子 | 1880-6821 | |||||
| DOI | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | 10.1585/pfr.12.1405023 | |||||
| 関連サイト | ||||||
| 識別子タイプ | URI | |||||
| 関連識別子 | http://www.jspf.or.jp/PFR/PFR_articles/pfr2017/pfr2017_12-1405023.html | |||||
| 関連名称 | http://www.jspf.or.jp/PFR/PFR_articles/pfr2017/pfr2017_12-1405023.html | |||||
