Monte Carlo simulation of Feynman-α and Rossi-α techniques for calculation of kinetic parameters of Tehran Research Reactor

Noise analysis techniques including Feynman-α (variance-to-mean) and Rossi-α (correlation) have been simulated by MCNP computer code to calculate the prompt neutron decay constant (α0), effective delayed neutron fraction (βeff) and neutron generation time (Λ) in a subcritical condition for the first operating core configuration of Tehran Research Reactor (TRR). The reactor core is considered to be in zero power (reactor power is less than 1 W) in the entire simulation process. The effect of some key parameters such as detector efficiency, detector position and its dead time on the results of simulation has been discussed as well. The results of proposed method in the current study are validated against both the experimental data and the results of MTR_PC computer code.

► We simulate Feynman-α and Rossi-α by MCNP computer code.
► The purpose is the calculation of kinetic parameters for Tehran Research Reactor.
► We examine the effects of efficiency and position of a detector on the results.
► We find that this modeling is only valid for high efficiency detectors.
► The applied methods are reliable tools for the calculation of kinetic parameters.