西村 正弘 
; 檜山 智之 ; 上出 英樹 ; 大島 宏之; 長澤 一嘉*; 今井 康友*
Nishimura, Masahiro; Hiyama, Tomoyuki; Kamide, Hideki; Ohshima, Hiroyuki; Nagasawa, Kazuyoshi*; Imai, Yasutomo*
The detailed flow velocity distribution in the edge subchannel has been obtained by PIV measurement using a wire-wrapped 3-pin bundle water model. These flow field data like flow velocity distribution and fluctuation intensity near the wrapping wire are available for code validation.
使用言語 |
: | English |
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掲載資料名 |
: | Proceedings of 9th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-9) (CD-ROM) |
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号 |
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ページ数 |
: | 7 Pages |
発行年月 |
: | 2014/11 |
発表会議名 |
: | 9th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-9) |
開催年月 |
: | 2014/11 |
開催都市 |
: | Buyeo |
開催国 |
: | Korea |
キーワード |
: | no keyword |
論文URL |
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論文解説記事 |
: | 燃料集合体内の狭く複雑な流路の冷却材流れを視る; インデックスマッチングにより高精度なPIV計測を実現[ |
Access |
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- Accesses |
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Altmetrics |
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