Influence of Iron in the Nucleation of ?c? Component Dislocation Loops in Irradiated Zircaloy-4 /

Influence of Iron in the Nucleation of ?c? Component Dislocation Loops in Irradiated Zircaloy-4 /

Under irradiation, the acceleration of growth of nuclear reactor components made of Zircaloy is clearly correlated to the presence of ?c? component dislocation loops. In the early stages, these loops appear to be essentially located close to the intermetallic precipitates. At higher doses, when ?c?...

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Bibliographic Details
Main Authors: de Carlan, Y. (Author), Gilbon, D. (Author), Griffiths, M. (Author), Lemaignan, C. (Author), Regnard, C. (Author)
Corporate Authors: ASTM International, American Society for Testing and Materials
Format: Book
Language:English
Published: West Conshohocken, Pa. : ASTM International, 1996
Subjects:
?c? dislocation loops
Congress
Fe supersaturation
Irradiation growth
Nuclear fuel claddings
Zirconium alloys
Zirconium
Zr alloys

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