In-core crack growth rate studies on irradiated austenitic stainless steels in BWR and PWR conditions in the Halden reactor

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

Volumn , Issue , 2005, Pages 337-348

  Karlsen, T M ^a   Bennett, P ^a   Hagberg, N W ^a  

^a OECD HALDEN REACTOR PROJECT   (Norway)

Author keywords

BWR; Crack growth rate; IASCC; Irradiated austenitic stainless steels; PWR; Stress intensity level; Yield strength

Indexed keywords

AUSTENITE; BOILING WATER REACTORS; CRACK PROPAGATION; MICROSTRUCTURE; STRESS INTENSITY FACTORS; YIELD STRESS;

CRACK GROWTH RATE; IRRADIATED AUSTENITIC STAINLESS STEELS; PWR; STRESS INTENSITY LEVEL;

STAINLESS STEEL;

EID: 33745245021     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (28)

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