A proposal of 200MW Inertial Confinement Fusion Fission Hybrid reactor which does not produce plutonium is presented on the basis of one dimensional discrete ordinate transport calculation and burmup calculation by using code BISON 1.5^[4].The time dependent results of energy deposit,²³⁸U(n,γ),239Pu(n,α),⁶Li(n,α) reac-tion rates and K_eff are given.Such a novel reactor proposed here not only could maintain high output power but also could keep critical safety.

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.

In this parper, the neutronics performance of a solid breeder blanket of a elementary designed fusion-fission hybrid experimental reactor has been studied in one-, two-, three-dimensional analysis and comparison. For being easy to describe the complicated geometry of the Tokamak torus, the neutron and gamma ray coupled transport calculation has been performed with the help of the Monte Carlo code MCNP. For avoiding uncertainties and errors involved in the generation and application of group constants and self-shielding effects, a continuous energy representation of the nuclear data base has been used.The main concern of the study has been the assessment of the spacial distribution of the tritium breeding ratio, the plutonium breeding ratio, and the power density in multi-dimensional configuration and the comparison between One-, two-, three-dimensional global calculation. The role and the limitation of one dimensional calculation has been pointed out.