Tritium diffusion in zircaloy-2 in the temperature range −78 to 204° C
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference21 articles.
1. Tritium diffusion in 304- and 316-stainless steels in the temperature range 25 to 222 °C
2. Diffusion coefficient of hydrogen in alpha zirconium, Zircaloy-2 and Zircaloy-4
3. Surface effects on the diffusion of tritium in 304-stainless steel and zircaloy-2
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1. Hydrogen diffusion coefficient in monoclinic zirconia in presence of oxygen vacancies;International Journal of Hydrogen Energy;2022-09
2. Interactions of hydrogen with zirconium alloying elements and oxygen vacancies in monoclinic zirconia;Acta Materialia;2022-02
3. Rate-limiting step of the deuterium desorption kinetics from Zircaloy-4 oxidized in PWR light primary water;International Journal of Hydrogen Energy;2021-11
4. Effect of the precipitates on the hydrogen desorption kinetics from zirconium-niobium alloys;International Journal of Hydrogen Energy;2021-02
5. Effect of a pre-oxidation on the hydrogen desorption from Zircaloy-4;Corrosion Science;2020-08
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