Analysis of MOX fuel behavior in reduced-moderation water reactor by fuel performance code FEMAXI-RM

Nuclear Engineering and Design

Volumn 227, Issue 1, 2004, Pages 19-27

  Suzuki, Motoe ^a   Saitou, Hiroaki ^a,b   Iwamura, Takamichi ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

^b CRC Solutions Inc   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

COOLANTS; FISSION PRODUCTS; IRRADIATION; NUCLEAR FUEL CLADDING; OXIDATION; PRESSURIZED WATER REACTORS; SWELLING; THERMAL CONDUCTIVITY;

FISSION GAS RELEASE;

NUCLEAR FUELS;

EID: 0242692571     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2003.08.001     Document Type: Article

References (17)

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