Role of doped ZrC on deuterium trapping in W-ZrC alloy
Understanding and predicting hydrogen isotopes (His) retention in plasma-facing materials (PFMs) is crucial for the safe and efficient operation of fusion reactors. Here, a new candidate PFM, W-ZrC alloy, was exposed to D plasma at temperatures in the range from 400 K to 850 K. Surface morphology an...
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| 主要な著者: | , , , , , , |
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| フォーマット: | Artigo |
| 言語: | Inglês |
| 出版事項: |
Elsevier
2025-12-01
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| シリーズ: | Nuclear Materials and Energy |
| 主題: | |
| オンライン･アクセス: | http://www.sciencedirect.com/science/article/pii/S2352179125001656 |
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