Thermal treatment of uranium oxide irradiated in pressurized water reactor: Swelling and release of fission gases

Journal of Nuclear Materials

Volumn 255, Issue 2-3, 1998, Pages 85-91

  Zacharie, I ^a   Lansiart, S ^a   Combette, P ^b   Trotabas, M ^c   Coster, M ^d   Groos, M ^e  

^a CEA SACLAY   (France)

^b DIF   (France)

^c COGEMA ^*  (France)

^d LERMAT Laboratoire d'Etude et de Recherche sur les Materiaux   (France)

^e ECOLE CENTRALE PARIS   (France)

Author keywords

[No Author keywords available]

Indexed keywords

COALESCENCE; DIFFUSION IN GASES; FISSION PRODUCTS; GRAIN BOUNDARIES; HEAT TREATMENT; IRRADIATION; POROSITY; PRESSURIZED WATER REACTORS; SWELLING; URANIUM COMPOUNDS;

FISSION GASES; URANIUM OXIDE;

NUCLEAR FUELS;

EID: 0032094810     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0022-3115(98)00039-7     Document Type: Article

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