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Impact of gas injection on detached plasma formation in divertor simulation experiments using the GAMMA 10/PDX tandem mirror
https://repo.qst.go.jp/records/72216
https://repo.qst.go.jp/records/722164c3bf499-42fe-448f-a4aa-f2aab78d0696
| Item type | 会議発表用資料 / Presentation(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2017-03-21 | |||||
| タイトル | ||||||
| タイトル | Impact of gas injection on detached plasma formation in divertor simulation experiments using the GAMMA 10/PDX tandem mirror | |||||
| 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 |
中嶋, 洋輔
× 中嶋, 洋輔× 市村, 和也× S., Islam M.× 坂本, 瑞樹× 江角, 直道× 福井, 良磨× 平田, 真史× 市村, 真× 池添, 竜也× 今井, 剛× M., Islam M.× 片沼, 伊佐夫× 假家, 剛× 小波蔵, 純子× 南, 龍太郎× 野尻, 訓平× 沼倉, 友晴× 大内, 理人× 清水, 弘慈× 寺門, 明紘× 吉川, 正志× Wang, X.× 朝倉, 伸幸× 福本, 正勝× 畑山, 明聖× 廣岡, 慶彦× 門, 信一郎× 久保, 博孝× 増崎, 貴× 松浦, 寛人× 仲野, 友英× 永田, 晋二× 西野, 信博× 大野, 哲靖× 相良, 明男× 澤田, 圭司× 庄司, 主× 利根川, 昭× 上田, 良夫× 中嶋 洋輔× 坂本 瑞樹× 朝倉 伸幸× 福本 正勝× 久保 博孝× 増崎 貴× 仲野 友英× 大野 哲靖× 相良 明男× 上田 良夫 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | This paper presents the detailed characteristics of the detached plasma produced in the GAMMA 10 PDX end-cell and especially focus on the comparison of the effects required for plasma detachment (such as radiation cooling) in various radiator gases (N2, Ne, Ar and Xe). GAMMA 10/PDX is the largest tandem mirror device in the world and high-power plasma heating systems are installed such as ion cyclotron range of frequency (ICRF) wave heating, electron cyclotron heating (ECH) and neutral beam injection (NBI) systems used in present-day fusion devices. By using these heating systems, high heat-flux generation and divertor simulation experiments under similar circumstances of actual fusion devices have been performed in the end-mirror region. So far the heat flux Pheat of ≥1 MW/m2 and the particle flux of 3.3e23 particles/s•m2 were achieved by using ICRF wave. Superimposing a short ECH pulse of ~400 kW into the ICRF-heated plasma attained the peak heat-flux value of more than 15 MW/m2 at the exit of west end-mirror. \nRecently, divertor simulation experiments using a divertor simulation experimental module (D-module) were started in the west end-cell. D-module is equipped with tungsten target plates mounted in V-shape and gas injection systems for investigating radiation cooling mechanism in order to characterize the plasma detachment produced in D-module. Arrays of Langmuir probes and calorimeters are also mounted on the target plates and behind gap of the V-shaped corner to measure the plasma parameters in detached state. \nIn detached plasma formation experiments from high temperature plasma (Ti ~150 eV, Te ~30 eV, ne ~1e18 m-3), effects of gas injection on the reduction of Te, the particle flux and the heating power onto the tungsten target were investigated. In cases of noble gases, it was found that Xe gas was most effective on electron cooling (down to 1~2 eV) and reduction of particle and heat fluxes (5~10%) and that Ne was less effective. On the other hand, N2 gas showed more favorable effects than Ar. Simultaneous injection of H2 and Xe drastically improved the performance for plasma detachment, which indicated the effect of molecular activated recombination (MAR) process. The results will be also discussed from the result of numerical simulation. |
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| 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 | 第22回制御核融合装置におけるプラズマ壁相互作用に関する国際会議 | |||||
| 発表年月日 | ||||||
| 日付 | 2016-05-30 | |||||
| 日付タイプ | Issued | |||||
