The response of alloy 690 tubing in a pressurized water reactor environment

Materials and Design

Volumn 28, Issue 2, 2007, Pages 373-379

  Young, B A ^a,b   Gao, Xiaosheng ^a   Srivatsan, T S ^a   King, Peter J ^b  

^a University of Akron   (United States)

^b BABCOCK AND WILCOX COMPANY   (United States)

Author keywords

Alloy 690; Environment; Fatigue crack growth; Model; Steam generator tubing; Temperature

Indexed keywords

CRACK PROPAGATION; FATIGUE OF MATERIALS; MICROSTRUCTURE; PLATES (STRUCTURAL COMPONENTS); STEAM GENERATORS; TEMPERATURE; TUBING;

FATIGUE CRACK GROWTH; STEAM GENERATOR TUBING; WATER REACTOR;

CORROSION FATIGUE;

CORROSION FATIGUE; CRACK PROPAGATION; FATIGUE OF MATERIALS; MICROSTRUCTURE; PLATES (STRUCTURAL COMPONENTS); STEAM GENERATORS; TEMPERATURE; TUBING;

EID: 33750360903     PISSN: 02613069     EISSN: 18734197     Source Type: Journal    
DOI: 10.1016/j.matdes.2005.10.001     Document Type: Article

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