Stress corrosion crack propagation rates in reactor vessel head penetrations in Alloy 600

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

Volumn , Issue , 1999, Pages 235-241

  Amzallag, Claude ^a   Vaillant, François ^a  

^a EDF R AND D   (France)

Author keywords

[No Author keywords available]

Indexed keywords

ACTIVATION ENERGY; CRACK PROPAGATION; DATA REDUCTION; EDDY CURRENT TESTING; INSPECTION; MICROSTRUCTURE; STRESS CORROSION CRACKING; STRESS INTENSITY FACTORS; SUPERALLOYS;

ALLOY 600; CRACK GROWTH RATE; REACTOR VESSEL HEAD; VESSEL HEAD PENETRATION;

PRESSURIZED WATER REACTORS;

EID: 0033489488     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1002/9781118787618.ch24     Document Type: Conference Paper

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