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The accuracy of new simple method of design calculation for neutron shielding in medical and industrial electron accelerator facilities, described in the preceding paper, is investigated in this work by comparing with the measured data in the actual facilities. For this comparison, several published data which have been measured in medical electron accelerator facilities were used, and in industrial facilities the measurement was performed in this work with a neutron dose equivalent meter. From the comparison of measured and calculated neutron dose equivalents, it was confirmed that this simple design method has sufficiently good accuracy.

radioisotopes

Shielding design and detection of neutrons from medical and industrial electron accelerators - Accuracy evaluation of simple calculation method by neutron measurement.