Cryogenic distillation: a fuel enrichment system for near-term tokamak-type D-T fusion reactors
The successful operation and economic viability of deuterium-tritium- (D-T-) fueled tokamak-type commercial power fusion reactors will depend to a large extent on the development of reliable tritium-containment and fuel-recycle systems. Of the many operating steps in the fuel recycle scheme, separation or enrichment of the isotropic species of hydrogen by cryogenic distillation is one of the most important. A parametric investigation was carried out to study the effects of the various operating conditions and the composition of the spent fuel on the degree of separation. A computer program was developed for the design and analysis of a system of interconnected distillation columns for isotopic separation such that the requirements of near-term D-T-fueled reactors are met. The analytical results show that a distillation cascade consisting of four columns is capable of reprocessing spent fuel varying over a wide range of compositions to yield reinjection-grade fuel with essentially unlimited D/T ratio.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 5562872
- Report Number(s):
- ANL-78-96; TRN: 80-007730
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
TOKAMAK TYPE REACTORS
FUEL CYCLE
TRITIUM RECOVERY
CRYOGENICS
DEUTERIUM
DISTILLATION
RECYCLING
TRITIUM
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
RADIOISOTOPES
RECOVERY
SEPARATION PROCESSES
STABLE ISOTOPES
THERMONUCLEAR REACTORS
YEARS LIVING RADIOISOTOPES
700206* - Fusion Power Plant Technology- Environmental Aspects
700205 - Fusion Power Plant Technology- Fuel
Heating
& Injection Systems