Experimental validation of a He-3 neutron detector Monte Carlo simulation model
Abstract
Gas filled neutron detectors are used for a variety of applications. In this work, a Monte Carlo simulation model of a He-3 neutron detector was made in MCNP5. For experimental validation of the detector model, the measured neutron counts at different neutron fields were compared with simulated neutron counts. A Cf-252 radioactive source was used to produce the neutron field, while neutron scattering and absorbing materials were used to vary the neutron energy distribution of the field. Simulation results showed that the different materials were able to vary the original neutron energy spectrum of the Cf-252. Subsequently, the simulated and measured neutron counts of the detector exposed to the neutron fields, were found to agree with reasonable uncertainty. Following the validation, the He-3 model can be utilized in the design of practical applications using the detector.
