Master curve evaluation of irradiated Russian VVER type reactor pressure vessel steels

Institution of Chemical Engineers Symposium Series

Volumn , Issue 148, 2000, Pages 109-124

  Viehrig, Hans W ^a   Boehmert, Juergen ^a   Dzugan, Jan ^a   Richter, Holger ^a  

^a INSTITUTE OF ION BEAM PHYSICS AND MATERIALS RESEARCH   (Germany)

Author keywords

Charpy V test; Fracture toughness; Integrity assessment; Predicting formulas; Radiation embrittlement; Reactor pressure vessel steel; Reference temperature; Transition temperature

Indexed keywords

ANNEALING; EMBRITTLEMENT; FRACTURE TOUGHNESS; NEUTRON IRRADIATION; NUCLEAR POWER PLANTS; PRESSURE VESSELS; PRESSURIZED WATER REACTORS;

REACTOR PRESSURE VESSEL STEELS;

STEEL TESTING;

EID: 0034462625     PISSN: 03070492     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (20)

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