Integrated analysis of VVER-1000 fuel assembly fueled with accident tolerant fuel (ATF) materials

Abstract

This paper presents an integrated study about some accident-tolerant fuels compared to the standard fuel in trying to find an alternative fuel that enhances the safety, competitiveness, and economics of commercial nuclear power. The neutronic, thermal–hydraulic and solid mechanics analysis of Uranium Nitride (UN) and Uranium Carbide (UC) were performed in a single fuel assembly of the VVER-1000 nuclear power reactor and compared with that of Uranium dioxide (UO2). MCNPX 2.7 computer code and COMSOL-Multiphysics computer software were used to make a deep analysis for the investigated fuel types. In the neutronic analysis, the fuel burn-up, the safety parameters and the power peaking factor (PPF) for the hot channel were simulated. The thermal–hydraulic and solid mechanics analyses were performed on the hot channel to make sure that the maximum temperature of the clad and the coolant would not exceed the safety limits.