OTR-experimental fusion-fission tokamak-reactor concept

An original concept of OTR-experimental hybrid fusion-fission tokamak-reactor is given. Tendencies to probable changes in the reactor parameters and some engineering alternatives are discussed. The feasibility of ''non-chemical'' fuel cycle with direct neutron enrichment (in the fusion-fission reactor blanket) of the fuel elements made of depleted uranium for their use in fission reactors is considered. Advantages and shortcomings of the blanket cooling with water, liquid metal and with a gas are briefly discussed. The parameters of experimental and commercial fusion-fission reactors and a composition of the nuclear fuel unloaded from such reactors are given. An option for the detail design which should be done by us needs some corrections in plasma geometry and in other parameters with account taken of new experimental and theoretical results, as well as that of the estimates and comparison of different engineering solutions referred to the plasma engineering, electrophysical and nuclear engineering aspects of the design. An initial OTR-concept, the tendencies to the correction of parameters and some engineering alternatives studied in the present stage of design are discussed in the paper. 12 refs, 2 tabs