Development and demonstration of ATR-MOX fuel

Abe, Tomoyuki; Maeda, Seiichiro ; Nakazawa, Hiroaki

Japan Nuclear Cycle Development Institute (JNC) developed plutonium and uranium mixed oxide (MOX) fuels for an advanced thermal reactor (ATR) for a flexible utilization of plutonium. JNC made endeavors to obtain well-homogenized MOX pellets by a ball mill mixing method with a variety of raw powders, including MOX powder by a microwave-heating denitration process. A total of 772 MOX fuel assemblies were utilized in the ATR prototype reactor

Language	:	English
Journal	:	Proceedings of 13th International Conference on Nuclear Engineering (ICONE-13)
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Pages	:	0 Pages
Publication Year/Month	:	2005/05
Meeting title	:	13th International Conference on Nuclear Engineering (ICONE-13)
Held date	:	2005/05
Location (city)	:	Beijing
Location (country)	:	China
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Registration No. : 08-2004-1269
JAEA Abstracts No. :
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