Abstract
A long counter is a commonly used device for neutron-flux measurements in a wide energy domain. Although its physical structure is well defined, device’s response differs significantly depending on the nature of radiation fields. We investigated a 3He long counter under well-defined radiation fields based on experiments and Monte Carlo simulations. The responses of the long counter were evaluated in MCNP6 and GEANT4 simulations for neutrons at energies between 10 keV and 20 MeV. The simulation results were validated with experimental data obtained with the spontaneous-fission neutron of 252Cf and quasi mono-energetic neutrons between 0.2 and 1.5 MeV. The results showed that MCNP6 underestimated count rates, calculated from the pulse-height distribution of recoiled particles in the neutron-induced nuclear reaction in the 3He volume, while neutron transportation seems equivalent in both simulation tools. For a given condition, GEANT4 reproduced the experimental values well, and GEANT4 results appeared to be more realistic for detector simulations in the energy range of interest.
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