Calculation of the Neutronic Parameters in Fast Nuclear Reactors by Using Monte Carlo Method

In this study, a computer program is implemented to calculate the neutronic parameters of a multiplier system by Monte Carlo method. This program is able to perform the calculation of various parameters such as the effective multiplication factor, neutron flux distribution, and effective delayed neutrons of the system. This program calculates the prompt and the total multiplication factor of neutrons separately, then it can be used to calculate the effective fraction of delayed neutrons by the use of the eigenvalues and also the prompt method. The results obtained for the effective neutron multiplication factor and the neutron flux distribution are compared with the experimental measurements and the results of using MCNP4C code. In this approach a good agreement between them was obtained. The comparison between the obtained results for the effective fraction of delayed neutrons of the prompt method with those of the experimental measuremants and other applied methods showed that the prompt method is a suitable approach for the calculation of the effective fraction of delayed neutrons.