SCC growth behavior of austenitic stainless steels in PWR primary water conditions

Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

Volumn , Issue , 2005, Pages 1029-1036

  Guerre, Catherine ^a   Raquet, Olivier ^a   Herms, Emmanuel ^a   Calvar, Marc Le ^b   Turluer, Guy ^b  

^a DIF   (France)

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

Author keywords

Crack growth; Stainless steels; Stress Corrosion Cracking

Indexed keywords

CRACK PROPAGATION; CYCLIC LOADS; FATIGUE OF MATERIALS; HIGH TEMPERATURE EFFECTS; PRESSURIZED WATER REACTORS; STRESS CORROSION CRACKING;

COMPACT TENSILE (CT) SPECIMENS; CYCLIC LOADING CONDITIONS; POST-MORTEM OBSERVATIONS; PRIMARY WATER CONDITIONS;

STAINLESS STEEL;

EID: 33745198883     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (15)

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