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The paper shows capabilities of thorium-lead fuel assembly for design of irradiation experiments on ThO 2  and natural UO 2  fuel samples using radioisotope neutron source. The main purpose of the current analysis was to determine the irradiation environment in the samples, especially: neutron spectrum, power, activity, reaction rates, production of  233 Pa and  239 Np as well as breeding of  233 U and  239 Pu. An advanced three-dimensional numerical model for Monte Carlo radiation transport and burnup simulations was developed using the Monte Carlo Continuous Energy Burnup Code (MCB). The versatility of the assembly gives a perfect opportunity to perform many irradiation experiments for R&amp;D on the thorium and uranium fuel cycle in a different material and geometrical environments.

Numerical design of thorium and uranium fuel samples irradiation in lead environment