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Compatibility of tritium permeation barrier coatings in water cooled ceramic breeder blanket

https://repo.qst.go.jp/records/83883
https://repo.qst.go.jp/records/83883
cc96860c-9eaf-4592-8503-7678d7cafe34
Item type 会議発表用資料 / Presentation(1)
公開日 2021-11-25
タイトル
タイトル Compatibility of tritium permeation barrier coatings in water cooled ceramic breeder blanket
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 object
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 近田拓未

× 近田拓未

WEKO 1012471

近田拓未

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Motoki, Nakajima

× Motoki, Nakajima

WEKO 1012472

Motoki, Nakajima

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鈴木亮権

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WEKO 1012473

鈴木亮権

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Suguru, Nakano

× Suguru, Nakano

WEKO 1012474

Suguru, Nakano

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Kim, Jaehwan

× Kim, Jaehwan

WEKO 1012475

Kim, Jaehwan

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大塚, 哲平

× 大塚, 哲平

WEKO 1012476

大塚, 哲平

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原, 正憲

× 原, 正憲

WEKO 1012477

原, 正憲

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Takashi, Nozawa

× Takashi, Nozawa

WEKO 1012478

Takashi, Nozawa

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Tsuyoshi, Hoshino

× Tsuyoshi, Hoshino

WEKO 1012479

Tsuyoshi, Hoshino

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Masaru, Nakamichi

× Masaru, Nakamichi

WEKO 1012480

Masaru, Nakamichi

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Motoki, Nakajima

× Motoki, Nakajima

WEKO 1012481

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Suguru, Nakano

× Suguru, Nakano

WEKO 1012482

en Suguru, Nakano

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Kim, Jaehwan

× Kim, Jaehwan

WEKO 1012483

en Kim, Jaehwan

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Takashi, Nozawa

× Takashi, Nozawa

WEKO 1012484

en Takashi, Nozawa

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Tsuyoshi, Hoshino

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WEKO 1012485

en Tsuyoshi, Hoshino

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Masaru, Nakamichi

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WEKO 1012486

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抄録
内容記述タイプ Abstract
内容記述 Strict control of tritium migration is an essential requirement for every blanket concept in a fusion reactor. Tritium permeation barriers (TPBs) have been developed in particular for liquid lithium-lead blankets using ceramic coatings; however, recent DEMO reactor design activities initiate an argument that a TPB is necessary also in solid breeder blankets. The previous studies revealed that reduced activation ferritic/martensitic (RAFM) steels and ceramic coatings reacted with solid breeder lithium ceramics under the blanket conditions, indicating the reactivity of solid breeders and its effect on tritium permeation should be taken into consideration. Moreover, not only the RAFM steel but the TPB will be exposed to pressurized water in a case where the TPB is applied to the cooling side. In this study, compatibility tests with pressurized water and lithium ceramic pebbles have been carried out for the investigation of the chemical stability of the TPB coatings and the effect on hydrogen isotope permeation in the Water Cooled Ceramic Breeder blanket.
会議概要(会議名, 開催地, 会期, 主催者等)
内容記述タイプ Other
内容記述 The 20th International Conference on Fusion Reactor Materials (ICFRM-20)
発表年月日
日付 2021-10-27
日付タイプ Issued
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Ver.1 2023-05-15 17:19:09.351243
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