High pulse number transient heat loads on beryllium
The experimental fusion reactor ITER will apply beryllium as first wall armor material. In present fusion experiments, e.g. ASDEX Upgrade, it has been detected that up to 25% of the plasma energy loss is deposited in non divertor regions during edge localized mode (ELM) events. Therefore, the impact...
| Main Authors: | , , , , |
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| 格式: | Article |
| 語言: | English |
| 出版: |
Elsevier
2017-08-01
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| 叢編: | Nuclear Materials and Energy |
| 在線閱讀: | http://www.sciencedirect.com/science/article/pii/S2352179116300515 |