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SOLPS-ITER Simulation Study for Power Exhaust in JA DEMO Divertor

https://repo.qst.go.jp/records/2003122
https://repo.qst.go.jp/records/2003122
9e14e4a5-dc7f-498e-9287-01bfa35b460a
アイテムタイプ 会議発表用資料 / Presentation(1)
公開日 2026-03-31
タイトル
タイトル SOLPS-ITER Simulation Study for Power Exhaust in JA DEMO Divertor
言語 en
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 presentation
著者 Si Hang

× Si Hang

Si Hang

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Kawamura Gakushi

× Kawamura Gakushi

Kawamura Gakushi

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Asakura Nobuyuki

× Asakura Nobuyuki

Asakura Nobuyuki

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Hoshino Kazuo

× Hoshino Kazuo

Hoshino Kazuo

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Seto Haruki

× Seto Haruki

Seto Haruki

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Sakamoto Yoshiteru

× Sakamoto Yoshiteru

Sakamoto Yoshiteru

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Yagi Masatoshi

× Yagi Masatoshi

Yagi Masatoshi

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抄録
内容記述 According to the physics design of JA-DEMO, the exhausted thermal power P_sep from the core plasma to the open field region reaching the wall surfaces, i.e., the scrape-off layer (SOL), is reported to 220 ~ 300 MW, which is much larger than ITER. Therefore, it is one of the biggest challenges for the design and operation of JA-DEMO to handle such a huge heat flux onto the plasma-facing components, especially the divertor targets. This motivates the exploration of possible solutions to dissipate power efficiently in the SOL and divertor region to ensure maximum steady-state power load at the divertor target below 10MW/m2 (the engineering limit of heat load for tungsten divertor target) in JA-DEMO. Now the SOLPS-ITER code is used to evaluate the effects of Ar seeding rate on divertor plasma. Under the different scenarios(Pcore/edge =250 and 300 MW), as Ar radiation impurity is increased from 1.0e19 to 1.0e20 atoms/s with the corresponding Ar concentration from 4 0.54% to 2.11%, the heat flux density and electron temperature at the divertor targets can be controlled well(<10MW/m^2) with low ne,sep = 2.0 ~ 3.5e19m-3.
会議概要(会議名, 開催地, 会期, 主催者等)
内容記述 IFERC-CSC Workshop on JFRS-1 Projects
発表年月日
日付 2025-06-04
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