Regular Article

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

AGH University of Science and Technology, Faculty of Energy and Fuels, Department of Nuclear Energy, al. Mickiewicza 30, 30-059 Krakow, Poland

^* e-mail: moettin@agh.edu.pl

Received: 11 February 2020
Received in final form: 14 April 2020
Accepted: 9 July 2020
Published online: 18 August 2020

Abstract

The paper shows capabilities of thorium-lead fuel assembly for design of irradiation experiments on ThO₂ and natural UO₂ 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 ²³³Pa and ²³⁹Np as well as breeding of ²³³U and ²³⁹Pu. 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&D on the thorium and uranium fuel cycle in a different material and geometrical environments.