Hydrogen diffusion process in the oxides formed on zirconium alloys during corrosion in pressurized water reactor conditions

Author:

Tupin Marc,Martin Frantz,Bisor Caroline,Verlet Romain,Bossis Philippe,Chene Jacques,Jomard François,Berger Pascal,Pascal Serge,Nuns Nicolas

Funder

M. Blat from EDF

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference41 articles.

1. Performance of alloy M5™ cladding and structure;Garner,2007

2. Behavior and properties of zircaloys in power reactors: a short review of pertinent aspects in LWR fuel;Garzarolli,1996

3. PWR comprehensive study of high burn-up corrosion and growth behavior of M5 and recrystallized low-tin zircaloy-4;Bossis,2008

4. Corrosion behavior of zircaloy-4 cladding with varying tin content in high-temperature pressurized water reactors;Garde,1994

5. Microstructure evolutions and iron redistribution in zircaloy oxide layers: comparative effects of neutron irradiation flux and irradiation damages;Iltis,1996

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