Vessel investigation program of "CHOOZ A" PWR reactor after shutdown

Institution of Chemical Engineers Symposium Series

Volumn , Issue 148, 2000, Pages 28-41

  Brillaud, Christian ^a   Grandjean, Yves ^a   Saillet, Sébastien ^a  

^a Electricite de France Industry Br   (France)

Author keywords

Charpy; Fracture toughness; Irradiation; Master curve; Reactor pressure vessel steel; Reactor shutdown; Reference temperature; Transition

Indexed keywords

EMBRITTLEMENT; FRACTURE TOUGHNESS; IRRADIATION; PRESSURE VESSELS; RADIATION DAMAGE; REACTOR SHUTDOWNS;

REACTOR PRESSURE VESSEL STEEL;

PRESSURIZED WATER REACTORS;

EID: 0034461252     PISSN: 03070492     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (4)

1. NDT toughness determination methodology using a new approach
2. A comparison between French surveillance program results and prediction of irradiation embrittlement
3. Fracture toughness of the Ni-modified A302-B plate of the BR3 reactor pressure vessel
4. Fracture toughness test results of precracked charpy specimens of irradiated 73W weld material