Pressurized thermal shock analyses of a reactor pressure vessel using critical crack depth diagrams

International Journal of Pressure Vessels and Piping

Volumn 76, Issue 12, 1999, Pages 813-823

  Jhung, Myung Jo ^a   Park, Youn Won ^a   Jang, Changheui ^b  

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

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

Author keywords

Crack arrest; Crack initiation; Critical crack depth; Pressurized thermal shock; Reactor pressure vessel; Structural integrity; Warm pre stressing

Indexed keywords

CRACK INITIATION; FINITE DIFFERENCE METHOD; FRACTURE TOUGHNESS; HEAT TRANSFER; NUCLEAR REACTORS; PRESSURE EFFECTS; STRESS CONCENTRATION; STRESS INTENSITY FACTORS; THERMAL STRESS;

CRACK ARREST; CRITICAL CRACK DEPTH DIAGRAMS; PRESSURIZED THERMAL SHOCK; STRUCTURAL INTEGRITY; WARM PRESTRESSING;

PRESSURE VESSELS;

CRACKING; NUCLEAR REACTOR; PRESSURE VESSEL; SHOCK; STRESS INTENSITY FACTOR;

EID: 0344182471     PISSN: 03080161     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0308-0161(99)00063-0     Document Type: Article

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