Validation of deterministic and probabilistic methods for calculating kinetic parameters with experimental reactivity in new configuration of HWZPR reactor core

The accurate calculation of effective kinetics parameters is very important in the study of time-dependent behavior of neutron populations.To calculate the parameters, it is necessary to calculate the flux and adjoint flux in the phase space, which can be calculated with deterministic and probability methods. In this paper, in order to obtain the kinetic parameters of the new configuration of the Isfahan heavy water zero power reactor core in a deterministic approach, the MTR-PC package has been used and in the probabilistic approach the developed mcnp code with Iterated Fission Probability (IFP) has been used.The kinetic parameters calculated by these methods are validated by comparing the response of the point kinetics and experimental values for a reactive injection, and a good agreement was found between the results of the calculations and the experimental values.