Predictive reactor pressure vessel steel irradiation embrittlement models: Issues and opportunities

JOM

Volumn 61, Issue 7, 2009, Pages 17-23

  Odette, G R ^a   Nanstad, R K ^b  

^a University of California   (United States)

^b OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ACCURATE PREDICTION; COPPER STEEL; CORRELATION MODELS; DUCTILE-BRITTLE TRANSITION TEMPERATURE; FLUENCES; IRRADIATION EMBRITTLEMENT; KEY VARIABLES; LOW FLUX; MASTER CURVE METHOD; NEW MODEL; NUCLEAR PLANT; REACTOR PRESSURE VESSEL STEELS; REIRRADIATION; SMALL SPECIMEN; SURVEILLANCE DATABASE; VESSEL STEEL;

BOILERS; CAISSONS; EMBRITTLEMENT; FRACTURE TOUGHNESS; GRAPH THEORY; PLANT LIFE EXTENSION; PRESSURE VESSELS; STEEL;

NEUTRON IRRADIATION;

EID: 70349736182     PISSN: 10474838     EISSN: 15431851     Source Type: Journal    
DOI: 10.1007/s11837-009-0097-4     Document Type: Review

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