Deuterium retention in tungsten under the combined influence of displacement damage and helium
Accurate predictions of hydrogen isotope/tritium inventory in tungsten (W), used as a plasma-facing material in fusion reactors, can reduce the uncertainty associated with the self-sustaining fuel cycle. It is well-established that displacement damage generally enhances deuterium (D) retention in W,...
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| Autors principals: | , , , , , , , , , |
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| Format: | Artigo |
| Idioma: | Inglês |
| Publicat: |
IOP Publishing
2025-01-01
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| Col·lecció: | Nuclear Fusion |
| Matèries: | |
| Accés en línia: | https://doi.org/10.1088/1741-4326/ade31a |
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