Abstract
MCNPX computer code is used to design a three-dimensional model for a typical Pressurized Water reactor (PWR) core. Uranium Nitride fuel (UN) was tested for the reactor and the results were compared with a typical UO2 fuel. Neutron spectrum, power distributions, plutonium isotopes productions, and kinetics and safety parameters were evaluated. It was found that thermal neutron spectrum is harder in UN than in UO2. UN can achieve a longer fuel residence time in the reactor than UO2. Kinetic and safety parameters are within the acceptable range similar to UO2. Control rod worth is lower in UN due to thermal flux hardening. This research was carried out with the addition of three types of variations of burnable poison.
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