Effects of thermal aging on the low cycle fatigue behavior of austenitic-ferritic duplex cast stainless steel

Nuclear Engineering and Design

Volumn 206, Issue 1, 2001, Pages 35-44

  Kwon, Jae do ^a   Woo, Seung wan ^a   Lee, Yong son ^a   Park, Joong cheul ^a   Park, Youn won ^b  

^a Yeungnam University   (South Korea)

^b Korea Institute of Nuclear Safety (KINS)   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

AGING OF MATERIALS; AUSTENITE; FATIGUE OF MATERIALS; FERRITE; STAINLESS STEEL; THERMAL CYCLING;

PRIMARY REACTOR COOLING SYSTEM;

NUCLEAR REACTORS;

EID: 0034818480     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(00)00408-8     Document Type: Article

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