Monte Carlo simulations using MCNP6.1 were performed to study the effect of neutron activation in Ar/CO2 neutron detector counting gas. A general MCNP model was built and validated with simple analytical calculations. Simulations and calculations agree that only the Ar-40 activation can have a considerable effect. It was shown that neither the prompt gamma intensity from the Ar-40 neutron capture nor the produced Ar-41 activity have an impact in terms of gamma dose rate around the detector and background level.