Plutonium and uranium recycle and neutron regeneration in a thermal power reactor

The problem of improving nuclear fuel utilization in thermal reactors is analyzed. A conceptual design of a HWGCR type power reactor is put forward which provides for increased conversion rates and approximately 15 per cent burnup of natural uranium used. 238U fuel with equilibrium concentrations of 239-241Pu and additions of 235U in the form of natural uranium is used. High fast neutron multiplication factors of the fuel, breeding blankets for neutron regeneration and U and Pu recycle provide for the high efficiency of the reactor. As applied to the KC-150 reactor core neutron balance and nuclear fuel optimum burnup are evaluated. The HWGCR type reactors utilizing the U-Pu fuel cycle are concluded to be able to expand substantially the nuclear fuel base of thermal power reactors