Abstract
Abstract Hydrogen isotope behavior and inventory in plasma-facing components (PFCs) of fusion devices are key concerns for safe, reliable, and economical operation. To accurately estimate hydrogen isotope retention and recovery in tungsten (the current leading candidate as a PFC), we have developed a model that was recently benchmarked against isotope depth profile and retention level in a tungsten target under various conditions and compared with both experimental data and simulation results. In this research, we have extended the model to include details of transient events. Therefore, one can use this model to estimate hydrogen isotope retention behavior in tungsten and potential other PFC candidates during normal operational pulse, effects of edge-localized modes (ELMs), and a possible cleaning processes scenario.
| Original language | English |
|---|---|
| Article number | 49186 |
| Pages (from-to) | 582-589 |
| Journal | Journal of Nuclear Materials |
| Volume | 465 |
| DOIs | |
| Publication status | Published - 6 Jul 2015 |
| Externally published | Yes |
UN SDGs
This output contributes to the following UN Sustainable Development Goals (SDGs)
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SDG 7 Affordable and Clean Energy
Research Keywords
- ELMs
- Fusion devices
- ITER
- Plasma-facing components
- Tritium retention
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