An optimization approach for cryogenic distillation-based protium removal systems in magnetic fusion energy fuel cycles
- Savannah River National Laboratory (SRNL), Aiken, SC (United States)
Tritium inventory reduction for fusion power plants is central to the successful adoption of fusion energy. The advent of direct internal recycling in deuterium-tritium fusion fuel cycle design has led to significant reduction in startup tritium inventory estimates for fusion power plants but requires an isotope rebalancing and protium removal (IRPR) system to ensure acceptable isotopic fuel composition. Cryogenic distillation is a potential solution for near-term deployment in an IRPR system due to its demonstrated performance in similar operating regimes. Using protium removal in the fuel cycle as the primary performance metric, this paper presents an optimization methodology for a single-column continuous cryogenic distillation-based IRPR system for a 500 MWfus magnetic fusion device. Distillation column optimization was performed using the CryOgenic Distillation For Isotopic Separation of Hydrogen (CODFISH) code developed at Savannah River National Laboratory. The distillation column design presented maximizes direct recycling of hydrogen isotopes from the fusion chamber exhaust to the fueling system while minimizing IRPR system steady-state tritium inventory. The optimized IRPR distillation column presented achieves direct recycling of 60 % of the hydrogen isotopes in the fusion chamber exhaust with an estimated steady-state system tritium inventory <30 g. The optimized IRPR distillation column operation was then used to estimate the design requirements for a detritation column to treat the IRPR system effluent stream.
- Research Organization:
- Savannah River National Laboratory (SRNL), Aiken, SC (United States)
- Sponsoring Organization:
- Fusion Energy Sciences; U.S. Department of Energy
- Grant/Contract Number:
- 89303321CEM000080
- OSTI ID:
- 3012645
- Report Number(s):
- SRNL-STI-2025-00574
- Journal Information:
- Fusion Engineering and Design, Journal Name: Fusion Engineering and Design Vol. 223; ISSN 0920-3796
- Publisher:
- Elsevier BVCopyright Statement
- Country of Publication:
- United States
- Language:
- English
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