Role of probabilistic analysis in integrity assessments of reactor pressure vessels exposed to pressurized thermal-shock conditions

Engineering Failure Analysis

Volumn 14, Issue 3, 2007, Pages 501-517

  Pugh, Claud E ^a   Richard Bass, B ^b   Dickson, Terry L ^b  

^a Oak Ridge Structural Assessments Inc   (United States)

^b OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

Experiments and probabilistic analysis; Nuclear power plant; Pressurized thermal shock

Indexed keywords

CRACK PROPAGATION; FAILURE ANALYSIS; FRACTURE MECHANICS; NUCLEAR POWER PLANTS; NUCLEAR REACTORS; PRESSURIZATION; PROBABILITY; RISK ASSESSMENT;

PRESSURIZED THERMAL-SHOCK; PROBABILISTIC FRACTURE MECHANICS; REACTOR PRESSURE VESSELS; THROUGH-WALL-CRACK DEVELOPMENT;

PRESSURE VESSELS;

CRACK PROPAGATION; FAILURE ANALYSIS; FRACTURE MECHANICS; NUCLEAR POWER PLANTS; NUCLEAR REACTORS; PRESSURE VESSELS; PRESSURIZATION; PROBABILITY; RISK ASSESSMENT;

EID: 33750884159     PISSN: 13506307     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.engfailanal.2005.08.006     Document Type: Article

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