Neutronic analysis of pebble bed moduler reactor with alternative fuels by using Monte Carlo method

In this study, the alternative fuel types were suggested for Pebble Bed Modular Reactor (PBMR) and the neutronic and burnup analysis were performed for the PBMR uses these fuel types. Suggested alternative fuel types were (WGP)O2+ThO2, (RGP)O2+ThO2, (MA)O2+ThO2 compositions. The MCNP 5 1.4 code was used for neutronic analysis while MONTEBURNS code was used for burnup analysis. The criticality (keff) of the reactor, neutron flux distribution and energy dependent neutron flux spectrum were observed for the each fuel type mentioned before. Finally, the burnup values of the PBMR fuel, the time dependent criticality and spent fuel content were analyzed.