Optimization of the Neutron Multiplier of Experimental Ayman Hybrid Blankets with ThO2

Abstract

At the college of Engineering, King Saud University, a research project has been initiated to lay out the


main structure of a prototypical experimental fusion and fusion-fission (hybrid) reactor blanket in cylindrical geometry. This geometry is consistent with most of the current fusion and hybrid reactor design


concepts in respect of the neutronic considerations. In this project the fusion chamber is simulated by


a cavity with a diameter of approximately 1.5 m inside a cylindrical blanket. Fusion neutrons of 14 MeV are


produced by a target movable along the axis of the cylinder. The movable neutron source will allow one to simulate a line source for integral experiments, which is a result of the linear nature of the Boltzmann Transport Equation. The present work analyses the effect of a neutron multiplier on the overall neutronic performance in the hybrid blanket. The studies have shown that a beryllium multiplier decreases the tritium breeding whereas the fissile breeding will be enhanced. On the other hand, a lead multiplier enhances, both, the fusile and fissile breeding ratios.