عنوان مقاله [English]
نویسندگان [English]چکیده [English]
In this paper, time dependent neutron transport in fissionable media is simulated by Monte Carlo method, and the neutronic parameters are estimated. In this article, the effective multiplication factor, neutron lifetime, and flux distribution in steady state condition are calculated. The comparison of the results obtained by this method, with those of the experimental measurements and the other calculations have shown that they are in very good agreement.