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  1. 原著論文

Development of benchmark reduced activation ferritic/martensitic steels for fusion energy applications

https://repo.qst.go.jp/records/48789
https://repo.qst.go.jp/records/48789
fafba262-0e20-4ed6-9fc3-ef8dfab52e9d
Item type 学術雑誌論文 / Journal Article(1)
公開日 2018-04-23
タイトル
タイトル Development of benchmark reduced activation ferritic/martensitic steels for fusion energy applications
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 谷川, 博康

× 谷川, 博康

WEKO 491324

谷川, 博康

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Gaganidze, E.

× Gaganidze, E.

WEKO 491325

Gaganidze, E.

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廣瀬, 貴規

× 廣瀬, 貴規

WEKO 491326

廣瀬, 貴規

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安堂, 正己

× 安堂, 正己

WEKO 491327

安堂, 正己

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Zinkle, S.J.

× Zinkle, S.J.

WEKO 491328

Zinkle, S.J.

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Lindau, R.

× Lindau, R.

WEKO 491329

Lindau, R.

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Diegele, E.

× Diegele, E.

WEKO 491330

Diegele, E.

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谷川 博康

× 谷川 博康

WEKO 491331

en 谷川 博康

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廣瀬 貴規

× 廣瀬 貴規

WEKO 491332

en 廣瀬 貴規

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安堂 正己

× 安堂 正己

WEKO 491333

en 安堂 正己

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抄録
内容記述タイプ Abstract
内容記述 Reduced-activation ferritic/martensitic (RAFM) steel is the benchmark structural material for in-vessel components of fusion reactor. The current status of RAFM developments and evaluations is reviewed based on two leading RAFM steels, F82H and EUROFER-97. The applicability of various joining technologies for fabrication of fusion first wall and blanket structures, such as weld or diffusion bonding, is overviewed as well. The technical challenges and potential risks of utilizing RAFM steels as the structural material of in-vessel components are discussed, and possible mitigation methodology is introduced. The discussion suggests that deuterium–tritium fusion neutron irradiation effects currently need to be treated as an ambiguity factor which could be incorporated within the safety factor. The safety factor will be defined by the engineering design criteria which are not yet developed with regard to irradiation effects and some high temperature process, and the operating time condition of the in-vessel component will be defined by the condition at which those ambiguities due to neutron irradiation become too large to be acceptable, or by the critical condition at which 14 MeV fusion neutron irradiation effects is expected to become different from fission neutron irradiation effects.
書誌情報 Nuclear Fusion

巻 57, 号 9, p. 092004, 発行日 2017-06
DOI
識別子タイプ DOI
関連識別子 10.1088/1741-4326/57/9/092004
関連サイト
識別子タイプ URI
関連識別子 http://iopscience.iop.org/article/10.1088/1741-4326/57/9/092004
関連名称 http://iopscience.iop.org/article/10.1088/1741-4326/57/9/092004
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