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Recent Developments of Plasma Exhaust and Divertor Design for Tokamak DEMO Reactors
https://repo.qst.go.jp/records/79432
https://repo.qst.go.jp/records/794326febbffb-6b42-450f-ab91-849945d04e81
| Item type | 会議発表用資料 / Presentation(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2020-03-15 | |||||
| タイトル | ||||||
| タイトル | Recent Developments of Plasma Exhaust and Divertor Design for Tokamak DEMO Reactors | |||||
| 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× Asakura, Nobuyuki |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | Conventional divertor concepts for recent DEMOs (P_fus=1.5-2GW, R_p=7-9m) were summarized. Requirements of fradmain and the plasma performance will determine divertor design concept. Approaches of two concepts, i.e. increasing f_rad^main (for ITER-level P_sep/R) and f_rad^div (for larger P_sep/R ~30MWm), will contribute to optimize future DEMO and power plant designs. Power exhaust simulations for DEMO divertor suggested that the total radiation fraction (f_rad = P_rad/P_heat >0.8) is required to reduce both peak-q_target and T_e,i. Improvements of lamda_q and detachment models are required. Outer leg length is similar: L_div=1.6-1.7 m and Width of q_// profile is lamda_q =2-3mm. Geometry effects (ITER like closer baffle or without baffle) on plasma detachment profile and the required radiation will be important key to operate the divertor in the low n_e^sep range. ITER-like target (W-PFC and Cu-alloy heat sink) is a common baseline design: for a year long operation, Re-Crystallization and Net-Erosion on W, and mechanical property of CuCrZr heat sink under n-irradiation will be anticipated. Restrictions of q_target , T_e,i and T_surface. Integrated design of divertor target, cassette and coolant pipe routing has been developed: two routes for W-PFC&Cu-alloy heat sink (lower-T) and RAFM steel heat sink for baffle/cassette (higher-T). Coolant-T (130-200C) and Cu-alloy property under n-irradiation are design issues. Water-cooled target components (incl. joint/inter layer) for high n-irradiation should be developed. |
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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 | 14th International Symposium on Fusion Nuclear Technology | |||||
| 発表年月日 | ||||||
| 日付 | 2019-09-27 | |||||
| 日付タイプ | Issued | |||||
