検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年

Oxidation behavior of UO$$_{2}$$ pellet at 673 - 1923 K

673-1923KにおけるUO$$_{2}$$ペレットの酸化挙動

鈴木 紀一  ; 砂押 剛雄*; McClellan, K. J.*; 加藤 正人   

Suzuki, Kiichi; Sunaoshi, Takeo*; McClellan, K. J.*; Kato, Masato

In a loss of coolant severe accident of a reactor core or a spent fuel pool, fuel pins are breached and oxidized at high temperatures. It was reported that oxidation of UO$$_{2}$$ pellets caused pulverization of the pellet and significant evaporation of UO$$_{3}$$ species. It is expected that those behaviors cause to spread the nuclear materials to environment. Therefore, understanding the oxidation behavior of UO$$_{2}$$ pellets is needed. In this preliminary investigation, oxidation behavior of UO$$_{2}$$ pellets was systematically investigated at wide range temperatures.

Access

:

- Accesses

InCites™

:

Altmetrics

:

[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.