SCC crack growth rate of cold-worked austenitic stainless steels in PWR primary water conditions

Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007

Volumn 1, Issue , 2007, Pages 676-699

  Guerre, Catherine ^a   Raquet, Olivier ^a   Herms, Emmanuel ^a   Marie, Stéphane ^b   Le Calvar, Marc ^c  

^a DIF   (France)

^b Laboratoire d'Etudes des Transferts et de Mécanique des Fluides   (France)

^c INSTITUT DE RADIOPROTECTION ET DE SÛRETÉ NUCLÉAIRE IRSN   (France)

Author keywords

Crack growth; Stainless steels; Stress corrosion cracking

Indexed keywords

AUSTENITIC STAINLESS STEEL; CHLORINE COMPOUNDS; CRACK PROPAGATION; CRACKS; NUCLEAR ENERGY; NUCLEAR FUELS; PRESSURIZED WATER REACTORS; RESIDUAL STRESSES; STAINLESS STEEL; STEEL CORROSION; STRAIN RATE; SULFUR COMPOUNDS; WATER TREATMENT;

CONTROLLING PARAMETERS; CYCLIC CRACK GROWTH; LABORATORY TEST; OXYGENATED ENVIRONMENTS; PWR ENVIRONMENTS; PWR PRIMARY WATERS; SCC INITIATION; SLOW STRAIN RATE TESTS;

STRESS CORROSION CRACKING;

EID: 51749110500     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

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