An investigation of lowering the fuel enrichment of MNSR was realized. A 3-
D neutronic model was developed for the analysis of the reactor. It was fou
nd that lower number of fuel elements is needed when UO2 is used with 5.45
g of U-235 content in each fuel rod. Sensitivity of the reactor to the puri
ty of the beryllium reflector proved to be an important factor in determini
ng the reactor neutronics as well as the weight of loaded fuel in the core.
Inherent safety features of low excess reactivity and shutdown margins are
preserved and enhanced. Average thermal fluxes over different zones of the
core are kept very much unchanged. (C) 1999 Elsevier Science Ltd. All righ
ts reserved.