LAUSR

Abstract The efficiency of fast neutrons generation in a deuterium tokamak plasma is analyzed. Tokamak parameters were estimated by relations of ITER Physics Basis. The parameters of D–D cycle are fundamentally different from the case of the D–T cycle with low tritium content. In an ITER scale tokamak with an aspect ratio A = 3, the gain and power are very low. In a D–D fuelled tokamak with A = 2 the power gain reaches Q ∼ 0.3. The efficiency of a fusion–fission hybrid system with the production of tritium in the D–D reaction was investigated. Two types of the tritium cycle are considered. In the first case, all tritium is burned in a catalyzed D–D cycle in a tokamak with A = 2. In the second case, some portion of tritium is burned in D–D based system, and some portion is used as a component of D–T fuel for a tokamak with A = 3 of relatively smaller size and greater efficiency.