Nakamura T
Radioisotopes. 1986 Feb;35(2):57-64. doi: 10.3769/radioisotopes.35.2_57.
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.
在前一篇论文中描述的用于医学和工业电子加速器设施中子屏蔽设计计算的新简单方法的准确性，在本工作中通过与实际设施中的测量数据进行比较来研究。为了进行这种比较，使用了在医学电子加速器设施中测量的几个已发表的数据，而在工业设施中，本工作使用中子剂量当量仪进行了测量。通过测量和计算的中子剂量当量的比较，证实了这种简单的设计方法具有足够好的准确性。
