Engineering Physics Annotation << Back POSSIBLE PARAMETERS OF NEUTRON SOURCE BASED ON TOKAMAK WITH TRITIUM OPERATION IN A DEUTERIUM PLASMA A.YU. CHIRKOV, D.E. FEDYUNIN The possibility of using the D–D reaction in a tokamak plasma to generate neutrons is considered. The efficiency is evaluated for the corresponding hybrid fusion–fission system using tritium produced in the D–D reaction in plasma. In such a system, there is no need to produce tritium in a blanket and, possibly, the production of fissile nuclear fuel per neutron increases. It is shown that in a tokamak with an aspect ratio A = 2, the gain in a deuterium plasma can reach Q ~ 0.3. Two versions of the hybrid system fuel cycle are considered. In the fi rst case, all the accumulated tritium is burned in the catalyzed D–D cycle in the tokamak with A = 2. In the second version, only 50% of tritium is burned, and 50% is used in the relatively small tokakamak with D–T fuel. Key words: fusion plasma, deuterium, tokamak. DOI: 10.25791/infizik.12.2018.335 Contacts: E-mail: chirkov@bmstu.ru Pp. 12-18.