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First SOLPS-ITER simulation study of Japanese DEMO on power exhaust and leakage of seeded Ar impurity

https://repo.qst.go.jp/records/2003121
https://repo.qst.go.jp/records/2003121
68bcf657-ce7b-407b-b8f5-b39801450642
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 First SOLPS-ITER simulation study of Japanese DEMO on power exhaust and leakage of seeded Ar impurity
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_6670
資源タイプ conference poster
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 For JA DEMO, a grand challenge is efficiently handling the extreme power loads onto plasma-facing components, particularly the divertor targets. Impurity seeding is an essential strategy for increasing the radiation losses and thereby reducing the heat load on the targets. A critical remaining issue is the trade-off between the retention of radiative impurities in the divertor region to maximize the radiation loss, and their escape to the upstream region, which degrades the core plasma confinement. To address this, based on the present baseline divertor geometry in JA DEMO, the SOLPS-ITER code is applied for the first time to evaluate the divertor power exhaust and Ar impurity distribution across various Ar seeding levels in detail. The simulation results show that increasing the Ar seeding level is highly beneficial for reducing the heat load on the targets. Moreover, in the near SOL there is a strong flow reversal of the main D ions and Ar impurity ions from the lower outer divertor target to the upstream. This flow reversal promotes the transport of Ar ions out of the lower outer divertor region, leading to significant core contamination. This leakage severely constrains the viability of using high seeding levels for heat load control in the current JA DEMO divertor geometry and plasma scenario.
会議概要(会議名, 開催地, 会期, 主催者等)
内容記述 20th International Workshop on Plasma Edge Theory in Fusion Devices (PET-20)
発表年月日
日付 2025-09-23
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