Release of fission tritium through Zircaloy-4 fuel cladding tubes
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference35 articles.
1. Hydrogen uptake during oxidation of zirconium alloys
2. Tritium technology for blankets of fusion power plants
3. Hydrogen ingress into oxidized Zr-2.5Nb
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1. Study on Tritium Production and Effluent Source Term for HPR1000;E3S Web of Conferences;2024
2. Trapping and diffusion of hydrogen in iron-doped Y2O3;Physical Chemistry Chemical Physics;2023
3. Estimation of tritium generation and discharge of the AP1000 reactor based on historical discharge data from the U.S. Pressurized water reactors;Nuclear Technology and Radiation Protection;2023
4. Rate-limiting step of the deuterium desorption kinetics from Zircaloy-4 oxidized in PWR light primary water;International Journal of Hydrogen Energy;2021-11
5. Kinetics of deuterium permeation through Zircaloy-4 in the 623–773 K temperature range;International Journal of Hydrogen Energy;2021-07
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