LAUSR

The prediction of nuclear reactor fuel burn-up rates throughout a reactors lifetime is an important problem in reactor core design. In this study, we present a novel algorithm called BuCal code. This code was used to perform burn-up analysis for a pressurized water reactor fuel with $${\text{UO}}_{2 }$$UO2 whose concentration is 19.5% enriched. Simulation results indicate that the total estimate of 235U consumption in 225 days with high neutron fluence is approximately 99.9% of the initial value. The study further showed that the microscopic absorption and fission cross sections decreases with increasing temperature and the concentrations of 235U and 238U decreases as the numbers of days increases while 236U build-up as the number of days increases.