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  1. 原著論文

Development of water-cooled blanket concept with pressure tightness against in-box LOCA for Japan’s DEMO

https://repo.qst.go.jp/records/49489
https://repo.qst.go.jp/records/49489
ec4e0e12-c860-4b98-a0ca-de137e5130d9
Item type 学術雑誌論文 / Journal Article(1)
公開日 2019-01-22
タイトル
タイトル Development of water-cooled blanket concept with pressure tightness against in-box LOCA for Japan’s DEMO
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 染谷, 洋二

× 染谷, 洋二

WEKO 871002

染谷, 洋二

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工藤, 広信

× 工藤, 広信

WEKO 871003

工藤, 広信

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飛田, 健次

× 飛田, 健次

WEKO 871004

飛田, 健次

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日渡, 良爾

× 日渡, 良爾

WEKO 871005

日渡, 良爾

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坂本, 宜照

× 坂本, 宜照

WEKO 871006

坂本, 宜照

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Special Design Team for Fusion DEMO, Joint

× Special Design Team for Fusion DEMO, Joint

WEKO 871007

Special Design Team for Fusion DEMO, Joint

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Someya, Yoji

× Someya, Yoji

WEKO 871008

en Someya, Yoji

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Tobita, Kenji

× Tobita, Kenji

WEKO 871009

en Tobita, Kenji

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Hiwatari, Ryoji

× Hiwatari, Ryoji

WEKO 871010

en Hiwatari, Ryoji

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Sakamoto, Yoshiteru

× Sakamoto, Yoshiteru

WEKO 871011

en Sakamoto, Yoshiteru

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抄録
内容記述タイプ Abstract
内容記述 A conceptual design of breeding blanket module with pressure tightness against in-box LOCA has been carried out, based on a pressurized water-cooled solid breeder blanket. The cooling water for DEMO is operated at the PWR water conditions of 15.5 MPa and 290 ºC-325 ºC. In this design, the breeding area of the module is divided into 0.1-m-squared cells with rib structure and has simple interior for mass production using a mixed pebbles bed of Li2TiO3 pebbles and Be12Ti ones. As a result, a rib with the thickness of 0.015m is needed to withstand the design pressure of 17.2 MPa by a stress analysis. The cooling system for the blanket module is designed by fluid dynamics analysis based on the PWR water conditions, and the outlet coolant temperature and the pressure drop are 321 ºC and 0.32 MPa, respectively. It was found that the self-sufficient production of tritium is likely to be satisfied with the blanket radial width thickness of 0.70 m or more and with an idea to improve TBR that the coolant is changed from existing light water to heavy water.
書誌情報 Fusion Engineering and Design

巻 146, p. 894-897, 発行日 2019-03
出版者
出版者 Elsevier
ISSN
収録物識別子タイプ ISSN
収録物識別子 0920-3796
DOI
識別子タイプ DOI
関連識別子 10.1016/j.fusengdes.2019.01.107
関連サイト
識別子タイプ URI
関連識別子 https://www.sciencedirect.com/science/article/pii/S0920379619301218?via%3Dihub
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