摘要
本文采用常规辐射监测仪器测试了^(241)镅—铍源机载源罐周围辐射场中的n、γ剂量当量率及其γ/n百分比值的分布规律。分析讨论了测试仪器、屏蔽材料与散射体对于中子测量结果的影响。探讨了在低剂量或低剂量率的受照情况下,利用γ辐射的监测数据,并通过γ/n百分比值估计中子或中子、γ总剂量当量,来评价中子测井人员的受照剂量。
The distribution of n, γ does equivelent ratio and γ: n persentage inradiation field around^(241) Am-Be source and its container as measured by usingconventional radiation menitor is analyzed in this paper. The effect of mo-nitoring instrument, shielding material and scatting material bodies on theneutron log measurement is also discussed. The goal of our study is to tryto estimate neutron or the total does equivelent of n, γ by using the moni-tored data of γ radiation and γ: n persentage to evaluate the radiation doesequivelent received by operating personnel under the circumstances ofradiation of low dose and low dose ratio.
