Stress corrosion crack propagation rate of Alloy 600 in the primary water of PWR influence of a cold worked layer

Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -

Volumn , Issue , 1999, Pages 207-214

  Raquet, O ^a   Santarini, G ^a  

^a DIF   (France)

Author keywords

[No Author keywords available]

Indexed keywords

CRACK INITIATION; CRACK PROPAGATION; FATIGUE OF MATERIALS; HYDROGEN; MORPHOLOGY; PRESSURIZED WATER REACTORS; RATE CONSTANTS; STRESS CORROSION CRACKING; STRESS INTENSITY FACTORS; VICKERS HARDNESS TESTING;

COLD WORKED ZONE; CONSTANT ELONGATION RATE TEST; PLASTIC STRAINING; PRIMARY WATER;

SUPERALLOYS;

EID: 0033489090     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1002/9781118787618.ch21     Document Type: Conference Paper

References (15)

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