The MCNP4C2 Monte Carlo code was used to model the Egyptian Second
research reactor in this paper, to calculate the effective multiplication factor
keff, distribution of the thermal and fast neutron fluxes and power in reactor
core with two type o
f fuels: standard and mixed. The values of the keff were
1.21842 and 1.05272, the maximum thermal flux were 2.975x10+14 and
3.352x10+14 n/cm2s, and the maximum fast flux was 2.950x10+14 and 2.389x10+14
n/cm2s for standard and mixed fuels respectively. The results showed good
agreements with previous results available in the literature.
