Corrosion and deuterium uptake of Zr-based alloys in supercritical water

Author:

Khatamian D.

Publisher

Elsevier BV

Subject

Physical and Theoretical Chemistry,Condensed Matter Physics,General Chemical Engineering

Reference16 articles.

1. Conceptual mechanical design for pressure-tube type supercritical water-cooled reactor;Yetisir,2011

2. Conceptual designs for advanced, high temperature CANDU reactors;Bushby,2000

3. Influence of environment on corrosion of zirconium and its alloys in high-temperature steam;Wanklyn;Journal of Electrochemical Society,1963

4. A.B. Johnson Jr., Corrosion and failure characteristics of zirconium alloys in high-pressure steam in temperature range 400 to 500°C, ASTM STP 458, 1969, p. 271.

5. B. Cox, Accelerated oxidation of Zircaloy-2 in supercritical steam, Report AECL 4448, Atomic Energy of Canada Ltd., April 1973.

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