Fusion-fission hybrid reactor with a plasma source of deuterium-tritium neutrons in a linear configuration

The separation of hydrogen isotopes is an important process in materials science, medicine, and nuclear energy. In this study, we attempted hydrogen isotope separation via electrolysis and H–D exchange reaction using LiCl–KCl–LiH–LiD molten salt at 673 K. In the molten-salt system, H and D exist as H− and D−, respectively, unlike that in the conventional aqueous solution. The diffusion coefficient of D− was determined by cyclic voltammetry in LiCl–KCl–LiD molten salt. Furthermore, H was enriched in the exhaust gas via both electrolysis and the H–D exchange reaction in molten LiCl–KCl containing equal quantities of LiH and LiD. D2 gas and H− are exchanged on a Pt-black catalyst in the molten salt.

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Fusion-fission hybrid reactor with a plasma source of deuterium-tritium neutrons in a linear configuration

Cited by 3 publications

References 27 publications

Mechanical and radiation shielding characterization of W-based alloys for advanced nuclear unit

Mechanical and radiation shielding characterization of W-based alloys for advanced nuclear unit

Neutron pumping of active medium formed by gadolinium isotopes 155Gd and 156Gd pair: A feasibility study

Deuterium Isotope Separation using LiCl–KCl–LiH–LiD Molten Salt

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