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

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.

Language	:	English
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Meeting title	:	Ceramic and Nuclear-focused Workshop
Held date	:	2012/05
Location (city)	:	Albuquerque
Location (country)	:	U.S.A.
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Keywords	:	no keyword
Research Facility	:	プルトニウム燃料製造施設
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Registration No. : BB20120178
JAEA Abstracts No. :
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Oxidation behavior of UO pellet at 673 - 1923 K

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