Abstract
The activation of a neutron generator is modeled for two operating scenarios: continuous for 16 h and 100 h at 4 h/day for one month. The distribution of the equivalent γ-ray dose rate was calculated for different times after the generator was shut down. Different grades of steel were considered for the material of the neutron generator flange. The time dependence of the γ-ray dose rate was calculated for each variant of steel. For long holding times, the steel 316L(N)-IG exhibits the lowest dose rate.
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