Abstract

The current manuscript presents a conceptual analysis of the hybrid tokamak operating with D–T plasmas in regimes with high values of the fusion gain Q (Q = fusion power output/auxiliary heating power input) or even in the ignition regime. The total fusion power release can reach \(P_{\text {fus}}\) = 150–200 MW. The key features of the hybrid system fusion–fission are a relatively small size and a construction simplicity of this plasma device (minor and major radii of the tokamak are \(a = 1.2\) m and \(R = 4.4\) m, respectively). It is assumed that the hybrid tokamak will operate in the so-called radiative improved (RI-)mode which has been extensively investigated in the tokamak TEXTOR-94 and other machines. This regime allows to overcome a range of practical difficulties existing nowadays to tokamak-reactors (for instance, the power exhaust). Additionally, the RI-mode gives a possibility to extend the operational limits, in particular, to increase considerably the plasma density. The main parameters of the designed tokamak have been obtained using a simple system code. The critical issues of using such a tokamak as a basis for a fusion neutron source or for a hybrid reactor device are discussed.

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