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Overview of test modules for Advanced Fusion Neutron Source A-FNS
https://repo.qst.go.jp/records/80265
https://repo.qst.go.jp/records/80265955251c8-bb6d-471f-84bd-c26123b5c9c1
| Item type | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2020-08-03 | |||||
| タイトル | ||||||
| タイトル | Overview of test modules for Advanced Fusion Neutron Source A-FNS | |||||
| 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 |
Sato, Satoshi
× Sato, Satoshi× Nakamura, Makoto× Kwon, Saerom× Ota, Masayuki× Park, ChangHo× Oyaizu, Makoto× Ochiai, Kentaro× Kasugai, Atsushi× Sakamoto, Keishi× Ishida, Shinichi× Satoshi, Sato× Kwon, Saerom× Masayuki, Ota× Park, ChangHo× Makoto, Oyaizu× Kentaro, Ochiai× Atsushi, Kasugai× Keishi, Sakamoto× Shinichi, Ishida |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | We have conducted a conceptual design on the test modules for Advanced Fusion Neutron Source A-FNS. Fusion neutron irradiation tests are performed using a variety of the test modules in A-FNS. We acquire the irradiation data on the fusion reactor materials, based on which the construction phase of the fusion DEMO DT reactor is to be decided. We established basic specifications and concepts on the test modules. Structural design on the test module was conducted taking into account the replacement with the remote handling, and we established the basic structural concept and the replacement methodology. By applying the methodology in this study, only capsules can be easily replaced from the test module. Nuclear analyses were performed for the test module. The maximum value of the neutron displacement damage on the blanket structural material test specimen is 10 dpa in accumulated irradiation for one year, and we can acquire the irradiation data on the cumulative damage of 20 dpa, which is requirement value as the initial irradiation data for the construction of a DEMO reactor, in accumulated irradiation for two years. Thermal analyses were conducted for the test specimens in irradiation, and it was confirmed their temperatures could satisfy the design specifications. |
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| 書誌情報 |
Fusion Engineering and Design 巻 155, 号 111714, p. 1-7, 発行日 2020-06 |
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| 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.2020.111714 | |||||
| 関連サイト | ||||||
| 識別子タイプ | URI | |||||
| 関連識別子 | https://www.sciencedirect.com/science/article/pii/S0920379620302623 | |||||
