The Effect of Microstructure on the Corrosion Behavior of Zircaloy-2 in BWRs

ASTM Special Technical Publication

Volumn , Issue 1354, 2000, Pages 658-677

  Etoh, Yoshinori ^a  

^a NIPPON NUCLEAR FUEL DEVELOPMENT CO LTD   (Japan)

Author keywords

Boiling water reactor; Cladding tube; Corrosion; Heat treatment; Hyrogen pickup; Irradiation induced dissolution; Second phase particle; Zircaloy 2

Indexed keywords

BOILING WATER REACTORS; CORROSION PREVENTION; CRYSTAL MICROSTRUCTURE; DISSOLUTION; HEAT TREATMENT; HYDROGEN EMBRITTLEMENT; IRON; METALLOGRAPHIC MICROSTRUCTURE; NEUTRON IRRADIATION; NICKEL; NUCLEAR FUEL CLADDING; RADIATION EFFECTS;

ZIRCONIUM ALLOY ZIRCALOY-2;

ZIRCONIUM ALLOYS;

EID: 0033902867     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Article

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