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,...
Збережено в:
| Автори: | , , , , , , , , , |
|---|---|
| Формат: | Artigo |
| Мова: | Inglês |
| Опубліковано: |
IOP Publishing
2025-01-01
|
| Серія: | Nuclear Fusion |
| Предмети: | |
| Онлайн доступ: | https://doi.org/10.1088/1741-4326/ade31a |
| Теги: |
Немає тегів, Будьте першим, хто поставить тег для цього запису!
|