Simulation of Pulsed Neutron Source Experiment in Tehran Research Reactor Core (TRR)

Abstract

One of the useful methods for measuring fast neutron decay constant in a nuclear reactor core is the pulsed neutron source experiment as MCNP code is based on the Monte Carlo method, so able to track the time-dependent behavior of the particles in static systems. In this research, this capability is utilized, and a pulsed neutron source experiment in the Tehran research reactor (TRR) core is simulated. For this purpose, the system of TRR core at different subcritical states is investigated, and fast neutron decay constant is estimated at each state. Therefore, kinetic parameters of the reactor core are also calculated utilizing the fast neutron decay constant of the core. Calculated values agree with the other results reported in the literature.

Keywords

• prompt neutron decay constant
• pulsed neutron source experiment
• mcnpx code
• reactor core kinetic parameter