Cryogenic Distillation: a Fuel Enrichment System for Near-Term Tokamak-Type D-T Fusion Reactors

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Description

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 ... continued below

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iv, 35 p. : charts, tables

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Misra, B. & Davis, J. F. February 1980.

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  • Main Title: Cryogenic Distillation: a Fuel Enrichment System for Near-Term Tokamak-Type D-T Fusion Reactors
  • Added Title: ANL (Series)
  • Added Title: Argonne National Laboratory Report ANL-78-96
  • Series Title: Argonne National Laboratory Reports

Description

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.

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iv, 35 p. : charts, tables

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  • February 1980

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  • Aug. 4, 2015, 8:33 a.m.

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  • Aug. 4, 2016, 2:04 p.m.

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Misra, B. & Davis, J. F. Cryogenic Distillation: a Fuel Enrichment System for Near-Term Tokamak-Type D-T Fusion Reactors, report, February 1980; Argonne, Illinois. (digital.library.unt.edu/ark:/67531/metadc303845/: accessed July 18, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.