Corrosion of Zirconium Alloys

(ZIRAT7/IZNA2 STR)
The microstructure in the Zr-Nb alloys have crucial impact on the material performance in-reactor. The microstructure is a function of material chemistry and the manufacturing process. This report provides an overview of Zr alloy manufacturing process and relationship between fabrication, microstructure and in-pile performance.

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Water Chemistry and CRUD Influence on Cladding Corrosion

(ZIRAT6/IZNA1 STR)
The purpose of the report is to describe the fundamentals in crud formation, transport, and deposition, in order to provide a solid basis for evaluating and analysing any fuel operational problem due to crud deposits. The ultimate purpose is to provide knowledge and insight for staff involved in the operation and materials selection in nuclear power plants, in order to prevent the occurrence of any crud-related fuel problems.

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Corrosion of Zr-Nb Alloys in PWRs

(ZIRAT9/IZNA4 STR)
The report gives an overview of the development of the Zr-Nb alloys in the nuclear industry, as well as the basic metallurgy and manufacturing of the Zr-Nb alloys. The report focuses on the out-of-reactor as well as in-reactor corrosion and hydrogen pickup performance.

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