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H-mode operation scenarios in JT-60SA initial research phase predicted by integrated core-pedestal-SOL/divertor simulation

https://repo.qst.go.jp/records/2002767
https://repo.qst.go.jp/records/2002767
767b6e03-d038-49da-a5dc-156310c40b56
アイテムタイプ 会議発表論文 / Conference Paper(1)
公開日 2026-02-12
タイトル
タイトル H-mode operation scenarios in JT-60SA initial research phase predicted by integrated core-pedestal-SOL/divertor simulation
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_5794
資源タイプ conference paper
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 Aiba Nobuyuki

× Aiba Nobuyuki

Aiba Nobuyuki

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Samuli Saarelma

× Samuli Saarelma

Samuli Saarelma

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Yamoto Shohei

× Yamoto Shohei

Yamoto Shohei

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Mitsuru Honda

× Mitsuru Honda

Mitsuru Honda

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Lorenzo Frassinetti

× Lorenzo Frassinetti

Lorenzo Frassinetti

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Arnaud Lafay-Labrosse

× Arnaud Lafay-Labrosse

Arnaud Lafay-Labrosse

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Hayashi Nobuhiko

× Hayashi Nobuhiko

Hayashi Nobuhiko

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Kazuo Hoshino

× Kazuo Hoshino

Kazuo Hoshino

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Umezaki Daisuke

× Umezaki Daisuke

Umezaki Daisuke

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Nakano Tomohide

× Nakano Tomohide

Nakano Tomohide

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Wakatsuki Takuma

× Wakatsuki Takuma

Wakatsuki Takuma

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内容記述タイプ Abstract
内容記述 An integrated simulation encompassing core-pedestal-SOL/divertor regions was performed for the first time in the world to establish H-mode operation scenarios in the JT-60SA initial research phase. The simulation demonstrated that the baseline H-mode scenario will achieve its target performance parameters for normalized beta β_N≥1.8 and energy confinement factor H_98y2≥1, while maintaining divertor heat flux well below maximum allowable limit q_∥<10MW/m^2 through controlled extrinsic impurity gas injection. This accomplishment addresses both ITER/DEMO-relevant operational objectives and scientific research priorities. The predictions were enabled by implementing advanced models and codes that analyze the complete plasma volume, with specific focus on achieving compatible density predictions between the SOL/divertor and pedestal regions to optimize both plasma performance and divertor heat load reduction. This integrated simulation framework significantly enhances predictive capabilities for future tokamak operations, providing essential insights for advancing research at JT-60SA, ITER, and next-generation fusion reactors.
書誌情報 Proceedings of 30th IAEA Fusion Energy Conference (IAEA FEC 2025)‎

発行日 2026-02
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