Mechanistic modelling of urania fuel evolution and fission product migration during irradiation and heating

Journal of Nuclear Materials

Volumn 362, Issue 2-3, 2007, Pages 327-335

  Veshchunov, M S ^a   Dubourg, R ^b   Ozrin, V D ^a   Shestak, V E ^a   Tarasov, V I ^a  

^a NUCLEAR SAFETY INSTITUTE   (Russian Federation)

^b INSTITUT DE RADIOPROTECTION ET DE SÛRETÉ NUCLÉAIRE IRSN   (France)

Author keywords

[No Author keywords available]

Indexed keywords

ANNEALING; CRYSTAL STRUCTURE; DEFECTS; FISSION PRODUCTS; FISSION REACTIONS; GRAIN BOUNDARIES; HEATING; HIGH TEMPERATURE EFFECTS; IRRADIATION; LOSS OF COOLANT ACCIDENTS; NUCLEAR FUELS;

FISSION ATOMS; FUEL OXIDATION; MECHANISTIC MODELING; MICROSCOPIC DEFECTS;

URANIUM DIOXIDE;

EID: 34247577636     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2007.01.081     Document Type: Article

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