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  1. 原著論文

Numerical and experimental study of coolant water flow in ITER divertor outer vertical target

https://repo.qst.go.jp/records/74936
https://repo.qst.go.jp/records/74936
fbe48199-b8e9-496d-a6b5-618eb43862bb
Item type 学術雑誌論文 / Journal Article(1)
公開日 2019-03-25
タイトル
タイトル Numerical and experimental study of coolant water flow in ITER divertor outer vertical target
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_6501
資源タイプ journal article
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 関, 洋治

× 関, 洋治

WEKO 1053854

関, 洋治

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江里, 幸一郎

× 江里, 幸一郎

WEKO 1053855

江里, 幸一郎

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鈴木, 哲

× 鈴木, 哲

WEKO 1053856

鈴木, 哲

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横山, 堅二

× 横山, 堅二

WEKO 1053857

横山, 堅二

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山田, 弘一

× 山田, 弘一

WEKO 1053858

山田, 弘一

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平山, 智之

× 平山, 智之

WEKO 1053859

平山, 智之

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平井, 武志

× 平井, 武志

WEKO 1053860

平井, 武志

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Yohji, Seki

× Yohji, Seki

WEKO 1053861

en Yohji, Seki

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Koichiro, Ezato

× Koichiro, Ezato

WEKO 1053862

en Koichiro, Ezato

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Satoshi, Suzuki

× Satoshi, Suzuki

WEKO 1053863

en Satoshi, Suzuki

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Kenji, Yokoyama

× Kenji, Yokoyama

WEKO 1053864

en Kenji, Yokoyama

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Hirokazu, Yamada

× Hirokazu, Yamada

WEKO 1053865

en Hirokazu, Yamada

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Tomoyuki, Hirayama

× Tomoyuki, Hirayama

WEKO 1053866

en Tomoyuki, Hirayama

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抄録
内容記述タイプ Abstract
内容記述 ITER divertor outer vertical target (OVT) consists of 22 plasma facing units (PFUs) and 2 stainless support structures (SSSs) including a complex internal structure for coolant water. Pressure drop and flow rate in each PFU are identified as important parameters for acceptable range in terms of the pumping power of cooling water system and performance of heat removal. In this study, computational fluid dynamics (CFD) and a transient reactor analysis code (TRAC-PF1) which is simpler simulation than the CFD have been performed to estimate the pressure drop and flow distribution in 11 PFUs mounted on an OVT SSS (half of the OVT). Results of both prediction methods showed the proper pressure drop and the homogeneous flow distribution within acceptable range of design requirement. To verify these numerical simulations, the results were compared to experimentally measured values in the flow test. This study demonstrated that the TRAC-PF1 as well as the CFD are applicable tools for further optimization of the divertor OVT cooling structure in view of manufacturing.
書誌情報 Fusion Engineering and Design

巻 136, 号 A, p. 420-425, 発行日 2018-11
出版者
出版者 Elsevier B.V.
DOI
識別子タイプ DOI
関連識別子 10.1016/j.fusengdes.2018.02.073
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