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  1. 原著論文

Safety research on fusion DEMO in Japan: Toward development of safety strategy of a water-cooled DEMO

https://repo.qst.go.jp/records/47846
https://repo.qst.go.jp/records/47846
95d741d1-5f51-4311-820c-066abf77d22e
Item type 学術雑誌論文 / Journal Article(1)
公開日 2017-04-27
タイトル
タイトル Safety research on fusion DEMO in Japan: Toward development of safety strategy of a water-cooled 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 中村, 誠

× 中村, 誠

WEKO 480307

中村, 誠

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飛田, 健次

× 飛田, 健次

WEKO 480308

飛田, 健次

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染谷, 洋二

× 染谷, 洋二

WEKO 480309

染谷, 洋二

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宇藤, 裕康

× 宇藤, 裕康

WEKO 480310

宇藤, 裕康

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坂本, 宜照

× 坂本, 宜照

WEKO 480311

坂本, 宜照

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Gulden, Werner

× Gulden, Werner

WEKO 480312

Gulden, Werner

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中村 誠

× 中村 誠

WEKO 480313

en 中村 誠

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飛田 健次

× 飛田 健次

WEKO 480314

en 飛田 健次

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染谷 洋二

× 染谷 洋二

WEKO 480315

en 染谷 洋二

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宇藤 裕康

× 宇藤 裕康

WEKO 480316

en 宇藤 裕康

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坂本 宜照

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WEKO 480317

en 坂本 宜照

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抄録
内容記述タイプ Abstract
内容記述 This paper reports the current status of a safety research on water-cooled fusion DEMO in Japan. A basic strategy of development of the safety guidelines is described for DEMO based on a water-cooled solid pebble bed blanket. Clarification of safety features of the DEMO in accident situations is a key issue to develop the guidelines. Recent achievements in understanding of the safety features of the water-cooled DEMO are reported. The MELCOR analysis has clarified the temperature histories of the DEMO components in a complete loss of decay heat removal event. The transient behavior of the first wall temperature is found to be essentially different from that of ITER. The pressure load to the tokamak cooling water system vault (TCWSV) is analyzed based on a simple model equation of the energy conservation. If the amount of the primary coolant is the same as that of Slim-CS, the previous small Japanese DEMO, the discharged water does not damage the TCWSV with the volume and pressure-tightness similar to those of pressurized light water reactors. It is shown that implementation of a pressure suppression system to the small TCWSV is effective to suppress the pressure load to the second confinement barrier.
書誌情報 Fusion Engineering and Design

巻 109/111, p. 1417-1421, 発行日 2016-11
出版者
出版者 Elsevier
DOI
識別子タイプ DOI
関連識別子 10.1016/j.fusengdes.2015.12.008
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