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Fusion Reactor Fuel Processing

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The Chemistry of Fusion Technology

Abstract

For thermonuclear power reactors based on the continuous fusion of deuterium and tritium the principal fuel processing problems occur in maintaining desired compositions in the primary fuel cycled through the reactor, in the recovery of tritium bred in the blanket surrounding the reactor, and in the prevention of tritium loss to the environment. Since all fuel recycled through the reactor must be cooled to cryogenic conditions for reinjection into the reactor, cryogenic fractional distillation is a likely process for controlling the primary fuel stream composition. Another practical possibility is the permeation of the hydrogen isotopes through thin metal membranes. The removal of tritium from the ash discharged from the power system would be accomplished by chemical procedures to assure physiologically safe concentration levels. The recovery process for tritium from the breeder blanket depends on the nature of the blanket fluids. For molten lithium the only practicable possibility appears to be permeation from the liquid phase. For molten salts the process would involve stripping with inert gas followed by chemical recovery. In either case extremely low concentrations of tritium in the melts would be desirable to maintain low tritium inventories, and to minimize escape of tritium through unwanted permeation, and to avoid embrittlement of metal walls.

This work was supported in part by U. S. Atomic Energy Commission Contract AT(11-1)-3073.

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References

  1. Barrer, R. M., Diffusion in and through Solids, Cambridge University Press, New York (1951).

    Google Scholar 

  2. Briggs, R. B., Tritium in Molten Salt Reactors, to be published.

    Google Scholar 

  3. Carlson, G. A., private communication (1972).

    Google Scholar 

  4. deRosset, A. J., Ind. Eng. Chem. 52, 525 (1960).

    Article  Google Scholar 

  5. Ditchburn, R. W., and Gilmour, J. C., Rev. Mod. Phys. 13, 310 (1941).

    Article  Google Scholar 

  6. Field, P. E., and Shaffer, J. H., J. Phys. Chem. 71, 3218 (1967).

    Article  Google Scholar 

  7. Flynn, T. M., Cryogenics 1, 2 (1960).

    Article  Google Scholar 

  8. Fookson, A., Pomerantz, P., Rothberg, S., J. Research NBS 47, 449 (1951).

    Google Scholar 

  9. Fraas, A. P., Nuclear Fusion Reactor Conference Proceedings, British Nuclear Energy Society, London, 1969, CLN-MFR, pp. 1–19.

    Google Scholar 

  10. Grimes, W. R., private communication (1972).

    Google Scholar 

  11. Heumann, F. K., and Salmon, O. N., The Lithium Hydride, Deuteride and Tritide Systems, Knoll Atomic Power Laboratory Report No. 1667 (Dec. 1956).

    Google Scholar 

  12. Johnson, E. F., Recovery of Tritium from Dilute Solutions of Lithium Tritide in Lithium, U.S. Atomic Energy Commission Report No. NYO-6371 (April 1956).

    Google Scholar 

  13. Kobisk, E. H., private communication (1972).

    Google Scholar 

  14. Mausteller, J. W., Tepper, F., Rodgers, S.J., Alkali Metal Handling and System Operating Techniques, Gordon and Breach, New York (1967).

    Google Scholar 

  15. Mittelhauser, A. M., and Thodos, G., Cryogenics 4, 368 (1964).

    Google Scholar 

  16. Mueller, W. M., Blackledge, J. P., and Libowitz, G. G., Metal Hydrides, Academic Press, New York (1968).

    Google Scholar 

  17. Perry, R. H., Chilton, C. H., Kirkpatrick, S. D., Perry’s Chemical Engineers’ Handbook, 4th ed., McGraw-Hill Book Co., New York (1963), pp. 9–40.

    Google Scholar 

  18. Princeton Plasma Physics Laboratory Reactor Studies Group, private communication (March 1972).

    Google Scholar 

  19. Rubin, L. R., Engelhard Industries Technical Bulletin VII, Nos. 1/2, 55 (1966).

    Google Scholar 

  20. Simons, J. H., ed. Fluorine Chemistry, Vol. I, Academic Press, New York (1950), Chap. 8.

    Google Scholar 

  21. Wilson, D. B., Study of the Drying Agent Anhydrous Magnesium Perchlorate, Doctoral Dissertation, Princeton University (1965).

    Google Scholar 

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© 1972 Plenum Press, New York

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Johnson, E.F. (1972). Fusion Reactor Fuel Processing. In: Gruen, D.M. (eds) The Chemistry of Fusion Technology. Springer, Boston, MA. https://doi.org/10.1007/978-1-4613-4595-4_5

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  • DOI: https://doi.org/10.1007/978-1-4613-4595-4_5

  • Publisher Name: Springer, Boston, MA

  • Print ISBN: 978-1-4613-4597-8

  • Online ISBN: 978-1-4613-4595-4

  • eBook Packages: Springer Book Archive

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