Minimizing MTR reactor uranium load with the use of MOX fuel by employing ORIGEN-S and MCNP4C codes

A computational study was performed for MTR reactors using ORIGEN-S and MCNP4C codes to replace some of the fuel elements (FEs) with MOX FEs. The results show that the replacement of the MTR-22 MW power research reactor Fes with MOX FEs leads to the reduction in the enrichment with 235U and the amount of loaded 235U in the core up to more than 20%. The amount of loaded uranium 235U FEs decreased considerably by increasing the number of MOX FEs. Re-evaluated neutronic parameters of the reactor showed that the replacement of the FEs by MOX FEs does not affect negatively the safe operational conditions of the reactor with practically no harmful effect on the safety of the reactor.