Behavior and properties of zircaloys in power reactors: A short review of pertinent aspects in LWR fuel

ASTM Special Technical Publication

Volumn 1295, Issue , 1996, Pages 12-32

  Garzarolli, F ^a   Stehle, H ^a   Steinberg, E ^a  

^a SIEMENS AG   (Germany)

Author keywords

Corrosion; Creep; In reactor corrosion; In reactor creep; Iodine stress corrosion; Irradiation growth; Neutron irradiation; Nuclear application; Operating conditions in LWRs; Precipitates; Radiation effects; Zircaloy 2 4; Zirconium alloys

Indexed keywords

COMPOSITION EFFECTS; CORROSION RESISTANT ALLOYS; CREEP; LIGHT WATER REACTORS; METALLOGRAPHIC MICROSTRUCTURE; NEUTRON IRRADIATION; NUCLEAR FUEL CLADDING; RADIATION EFFECTS;

ZIRCONIUM ALLOY ZIRCALOY 2; ZIRCONIUM ALLOY ZIRCALOY 4;

ZIRCONIUM ALLOYS;

EID: 0030287486     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/stp16165s     Document Type: Review

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