Ductility and strain rate sensitivity of Zircaloy-4 nuclear fuel claddings

Journal of Nuclear Materials

Volumn 295, Issue 1, 2001, Pages 21-26

  Lee, K W ^a   Kim, S K ^a   Kim, K T ^b   Hong, S I ^a  

^a Chungnam National University   (South Korea)

^b Korea Electric Power Research Institute (KEPRI)   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

AGING OF MATERIALS; DUCTILITY; NUCLEAR REACTORS; PLASTIC FLOW; STRAIN RATE; STRENGTHENING (METAL); THERMAL EFFECTS; ZIRCONIUM ALLOYS;

STRAIN AGING;

NUCLEAR FUEL CLADDING;

EID: 0035336507     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0022-3115(01)00509-8     Document Type: Article

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