Nucleation and Growth of Intermetallic Precipitates in Zircaloy-2 and Zircaloy-4 and Correlation to Nodular Corrosion Behavior /

One of the fundamental aspects in the history of the development of zirconium alloys for nuclear applications is the corrosion behavior under in-pile conditions. In boiling-water reactors (BWRs) and pressurized-water reactors (PWRs) the zirconium alloys Zircaloy-2 and Zircaloy-4 are the most commonl...

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Bibliographic Details
Main Authors: Maussner, G. (Author), Steinberg, E. (Author), Tenckhoff, E. (Author)
Corporate Authors: ASTM International, American Society for Testing and Materials
Format: Book
Language:English
Published: West Conshohocken, Pa. : ASTM International, 1987
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