Deuterium retention in self-damaged tungsten
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference26 articles.
1. Hydrogen exchange with voids in tungsten observed with TDS and PA
2. Deuterium retention and release from highly irradiated annealed tungsten after exposure to a deuterium DC glow discharge
3. Deuterium trapping in ion-damaged tungsten single crystal
4. Deuterium trapping in tungsten damaged by high-energy hydrogen ion irradiation
5. Hydrogen behavior in damaged tungsten by high-energy ion irradiation
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1. The effect of atomic hydrogen on the behavior of a single dislocation of 〈111〉{112} in bcc tungsten: Atomistic study;Journal of Nuclear Materials;2024-02
2. A critical review of experiments on deuterium retention in displacement-damaged tungsten as function of damaging dose;Materials Research Express;2023-10-01
3. Effect of 5 MeV Au3+ ions irradiation damage on surface blistering and deuterium retention behaviors in W and W-ZrC alloy;Nuclear Materials and Energy;2023-09
4. The effect of pre-damage distribution on deuterium-induced blistering and retention in Tungsten;Fusion Engineering and Design;2023-04
5. Deuterium retention in tungsten studied by sequential implantations at ELM-relevant energies;Nuclear Materials and Energy;2023-03
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