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

摘要

Noise analysis techniques including Feynman-a (variance-to-mean) and Rossi-a (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 (A) 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.