Corrosion fatigue crack growth behaviour of low-alloy reactor pressure vessel steels under boiling water reactor conditions

Corrosion Science

Volumn 50, Issue 7, 2008, Pages 1884-1899

  Seifert, H P ^a   Ritter, S ^a  

^a PAUL SCHERRER INSTITUTE   (Switzerland)

Author keywords

A. Low alloy steel; C. Corrosion fatigue; C. Reactor conditions

Indexed keywords

ALLOYS; AUTOCLAVES; BOILERS; BOILING LIQUIDS; BOILING WATER REACTORS; CAISSONS; CODES (STANDARDS); CODES (SYMBOLS); COMPRESSED AIR; CORROSION; CRACK DETECTION; CRACK PROPAGATION; CRACKING (CHEMICAL); CRACKS; CURVES (ROAD); ECOLOGY; FATIGUE CRACK PROPAGATION; FATIGUE OF MATERIALS; FATIGUE TESTING; FRACTURE FIXATION; FRACTURE MECHANICS; HYDROGEN; NUCLEAR REACTORS; PRESSURE; PRESSURE VESSEL CODES; PRESSURE VESSELS; REACTION KINETICS; STEAM POWER PLANTS; STRENGTH OF MATERIALS; TWO PHASE FLOW; WATER COOLED REACTORS;

(I ,J) CONDITIONS; BOILING WATER; CORROSION FATIGUE CRACK GROWTH; ELSEVIER (CO); EXISTING CODES; EXPERIMENTAL DATA; FATIGUE CRACK GROWTH (FCG); FATIGUE CRACK GROWTH CURVES; FATIGUE TESTS; HIGH-PURITY; HYDROGEN WATER CHEMISTRY (HWC); LOADING PARAMETERS; LOW ALLOY; LOW FREQUENCY (LF); REACTOR PRESSURE VESSEL (RPV); REACTOR PRESSURE VESSEL (RPV) STEEL; RPV STEELS; SUPERPOSITION MODEL; SYNERGISTIC EFFECTS (SE); TIME DOMAIN (OCT);

CORROSION FATIGUE;

EID: 47049117552     PISSN: 0010938X     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.corsci.2008.03.010     Document Type: Article

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