Abstract
Cryopump-based direct internal recycling (DIR) of fusion fuel is an attractive prospect because it provides pumping of helium ash from a reactor along with separation of helium and other impurities from the fuel. Previous studies have demonstrated a continuously regenerating cryopump, referred to as the Snail pump, that separates helium ash from fusion fuel for reactor-relevant flow rates. In this study, a conceptual cryopump was designed as a proof-of-principle study to target other impurities, besides helium ash, from the fusion exhaust that would complement the Snail pump. The impurity-removal cryopump consists of four sets of chevron fins, two sets operating at 80 K and the other two at 30 K. A computational study using direct simulation Monte Carlo (DSMC) was performed with a gas mixture of 96.5% D2, 2.0% He, and 0.5% each of CO2, N2, and CH4. In this configuration, 80 K chevron fin sets are capable of capturing CO2 and 30 K sets capable of capturing CO2, N2, and CH4. The computational study showed that the cryopump is capable of reducing the impurity content by more than two orders of magnitude from the flow.
| Original language | English |
|---|---|
| Journal | IEEE Transactions on Plasma Science |
| DOIs | |
| State | Accepted/In press - 2025 |
Funding
The U.S. Gtvo retains and the ,publisher by accept- ing the orkw for publication, wledgesackno that the U.S. Gtvo retains a e,vxclusinone paid-up, ocable,virre orldwidew license to publish or reproduce the submitted manuscript ersionv of this ork,w or wallo others to do so, for U.S. Gtvo purposes. DOE will videpro public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (https: public-access-plan). This research used resources of the Compute and Data Etn for Science (CADES) at the Oak Ridge National L,a which is supported by the Office of Science of the U.S. Department of Energy under Contract No. DEAC0500OR22725.
Keywords
- Cryopump
- direct internal recycling (DIR)
- direct simulation Monte Carlo (DSMC)
- fusion fuel cycle
- impurity removal
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