Abstract: In this paper the power flow, tritium and plutonium fuel cycle and the possibility of earlier application of the hybrid reactor as fusion energy source have been introduce briefly. A preliminary neutronics study and design of the fast-fission blanket and the suppressed-fission blanket have been performed. The strong and weak point of different blankets and its application prospects have been pointed out.

Key words: inertial confinement, hybrid reactor, energy multiplication, Pu-239 braiding ratio, support ratio