Radiation-induced degradation of stainless steel light water reactor internals

Materials Science and Engineering R: Reports

Volumn 73, Issue 7-8, 2012, Pages 67-83

  Kenik, Edward A ^a   Busby, Jeremy T ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

Creep; Embrittlement; Irradiation induced stress corrosion cracking; Light water reactor; Point defect clustering; Point defects; Radiation damage; Radiation hardening; Radiation induced degradation; Radiation induced precipitation; Radiation induced segregation; Swelling; Transmutation effects; Voids

Indexed keywords

CRACKS; CREEP; EMBRITTLEMENT; HARDENING; IRRADIATION; POINT DEFECTS; PRECIPITATION (CHEMICAL); RADIATION DAMAGE; RADIATION HARDENING; RESIDUAL STRESSES; SEGREGATION (METALLOGRAPHY); STAINLESS STEEL; STEEL CORROSION; STRESS CORROSION CRACKING; SWELLING;

INDUCED STRESS; POINT DEFECT CLUSTERING; RADIATION-INDUCED; RADIATION-INDUCED DEGRADATION; RADIATION-INDUCED SEGREGATION; TRANSMUTATION EFFECTS; VOIDS;

LIGHT WATER REACTORS;

EID: 84864779040     PISSN: 0927796X     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.mser.2012.05.002     Document Type: Review

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