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Accumulated 2-D neutron flux distribution during KSTAR operation
https://repo.qst.go.jp/records/74901
https://repo.qst.go.jp/records/74901f8c727df-c263-468d-b5ae-700b6d458f48
| Item type | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2019-03-22 | |||||
| タイトル | ||||||
| タイトル | Accumulated 2-D neutron flux distribution during KSTAR operation | |||||
| 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 |
Jong-Gu, Kwak
× Jong-Gu, Kwak× Lee, Y.S.× Lee, D.R.× Kim, C.S.× Kim, H.S.× Lee, H.J.× 篠原, 孝司× Koji, Shinohara |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | Since the successful first H-mode in 2010, duration of H-mode is extended to 1 min and the highest stored plasma energy up to 0.6 MJ is obtained by developing hybrid and internal transport barrier (ITB) mode as well as typical H-mode. Major heating system is the neutral beam (NB) of 100 keV with 5.5 MW and it is planned that the new additional 6 MW NBI is installed in 2018. So there is a lot of production of fast neutrons coming from via D (d,n)3He reaction and it is found that most of neutrons are 2.45 MeV neutrons coming from deuterium beam plasma interaction and the total neutron fluence during a campaign could be estimated to be about 1019. In particular, several nickel activation samples are installed inside/outside the vacuum vessel poloidally and tor- oidally and the total accumulated neutron flux is estimated from 811 keV gamma emission measurement after the campaign. The results show that the neutron activation both inside and outside the vacuum vessel has toroidally non-axisymmetric distribution and it has the highest neutron flux around poloidal limiter area. Considering the prompt ion loss at nominal KSTAR operation including the high beta-p operation, prompt loss ions from 100 keV neutral ion beams hitting on three poloidal limiters was not negligible and the non-uniform distribution is discussed in term of prompt ion loss to the poloidal limiter. In addition, this work reports on the quantitative analysis of poloidal distribution of the neutron emission based on accumulated flux measurements. | |||||
| 書誌情報 |
Fusion Engineering and Design 巻 136, p. 777-781, 発行日 2018-04 |
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| 出版者 | ||||||
| 出版者 | Elsevier | |||||
| DOI | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | 10.1016/j.fusengdes.2018.04.008 | |||||
| 関連サイト | ||||||
| 識別子タイプ | URI | |||||
| 関連識別子 | https://www.sciencedirect.com/science/article/pii/S0920379618302965 | |||||
