Abstract
Steady state tokamak with deuterium–tritium plasma is considered as a basis for fusion neutron source for a hybrid fusion–fission reactor. Prototypes of such a system can be developed on the basis of the present day tokamaks as the plasma power gain factor Q ~ 1 is required for hybrid applications. Significant population of fast ions can be supported by a powerful neutral beam injection heating in regimes with Q ~ 1. The reaction rate for fast ions greatly exceeds the rate for thermal Maxwellian ions. The possible ranges of parameters are discussed for medium size tokamaks with minor plasma radius a = 0.5–1 m. Power and sizes of the neutron source are determined by the value of the injection energy. Power gain Q ≈ 1 can be achieved with injection energy of deuterium about 130 keV and tritium energy about 200 keV. Neutron power of 30–40 MW can be realized with a ≈ 1 m, and about of few megawatts with a ≈ 0.5 m.
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Work was supported by the Russian Ministry of Education and Science, the Contract No. 13.2573.2014/K.
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Almagambetov, A.N., Chirkov, A.Y. Power and Sizes of Tokamak Fusion Neutron Sources with NBI-Enhanced Reaction Rate. J Fusion Energ 35, 841–848 (2016). https://doi.org/10.1007/s10894-016-0111-0
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DOI: https://doi.org/10.1007/s10894-016-0111-0