and zircaloy-2とジルカロイ-2から成るコリウムの物性に及ぼす酸素・金属比の影響廣岡 瞬 
; 加藤 正人 
; 森本 恭一 ; 米野 憲 ; 内田 哲平; 赤司 雅俊
Hirooka, Shun; Kato, Masato; Morimoto, Kyoichi; Komeno, Akira; Uchida, Teppei; Akashi, Masatoshi
In order to evaluate the method to clean up molten corium generated in the severe accident of reactor melt down, physical properties such as melting temperature and thermal conductivity are necessary. In this study, corium which simulates the molten core of a BWR was prepared from UO and zircaloy-2. Oxygen to metal (O/M) ratio of the corium was adjusted to hyper-stoichiometry, and the physical properties were investigated.
使用言語 |
: | English |
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掲載資料名 |
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巻 |
: | 437 |
号 |
: | 1-3 |
ページ数 |
: | p.130 - 134 |
発行年月 |
: | 2013/06 |
発表会議名 |
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開催年月 |
: | 2012/10 |
開催都市 |
: | Osaka |
開催国 |
: | Japan |
キーワード |
: | 福島第一原子力発電所事故; Fukushima Daiichi Nuclear Power Station Accident |
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論文解説記事 |
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Access |
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- Accesses |
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パーセンタイル：38.62 分野：Materials Science, Multidisciplinary |
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