Corrosion of titanium alloys in pressurised water at 350 °C and 17.5 MPa

Author:

Selva Sabrina,Bignon Quentin,Raynal Amandine,Martin Frantz,Auzoux Quentin,Renou Gilles,Latu-Romain Laurence,Wouters Yves

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference15 articles.

1. M. Zucchetti, D. Boerman, G. Piatti, Characterization of a titanium alloy for nuclear fusion applications, in: Proc. 6-th International Meet. on Titanium, Torino, 1990, p. 18.1.

2. Oxide formation on titanium alloys in primary water of nuclear pressurised water reactor;Bignon;Corros. Sci.,2019

3. Corrosion of titanium alloys in pressurised water at 300 °C: kinetics and modelling;Selva;Corros. Sci.,2021

4. A new model to predict the oxidation kinetics of zirconium alloys in a pressurized water reactor;Bouineau;J. ASTM Int.,2008

5. General corrosion properties of titanium based alloys for the fuel claddings in the supercritical water-cooled reactor;Kaneda;Conf. Environ. Degrad. Mater. Nucl. Power Syst. React. Miner. Met. Mater. Soc.,2005

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