calculation of neutronic and kinetic parameters of isfahan miniature neutron source reactor using slope fit and perturbation methods

Kinetic and neutronic parameters play an important role in analysis of reactors dynamic behavior. some of these parameters include effective multiplication factor (keff), reactivity (ρ), neutron flux and power spatial distributions, effective delayed neutron fraction (βeff) and prompt neutron lifetime (ℓp). in this work, monte carlo modeling and analysis of isfahan miniature neutron source reactor (mnsr) has been performed for calculation of the kinetic and neutronic parameters using mcnpx2.6 code, slope fit and perturbation methods. relative differences between the results of mcnpx2.6 code in calculation of ρ and βeff and the reference values are about 0.5% and 2.1%, respectively. k eywords mnsr neutronic and kinetic parameters slope fit method perturbation method mcnpx2.6 code the relative differences between the results of the slope fit and perturbation methods and mcnpx2.6 code in calculation of the ℓp parameter and the reference values are about 17.6%, 4.8% and 29.19%, respectively. therefore, the results of these research show that the mcnpx2.6 code can be appropriate for calculation of the reactor kinetic parameters such as βeff, while the perturbation method is a simple and convenient method for calculating ℓp.