Radiation dose estimation and protective measure discussion of 241Am-Be neutron source logging
10.13491/j.issn.1004-714X.2022.02.007
- VernacularTitle:241Am-Be中子源测井的辐射剂量估算与防护措施探讨
- Author:
Yaping FU
1
;
Yuan YAN
1
;
Zhengwei YU
2
;
Liangping CHEN
1
;
Linghai KONG
2
;
Peng SUN
1
Author Information
1. China Institute of Atomic Energy, Beijing 102413 China.
2. Nuclear and Radiation Safety Center, Beijing 100082 China.
- Publication Type:OriginalArticles
- Keywords:
241Am-Be neutron source;
Logging;
Dose equivalent rate;
Effective dose
- From:
Chinese Journal of Radiological Health
2022;31(2):167-171
- CountryChina
- Language:Chinese
-
Abstract:
Objective To investigate the radiation dose to operators in the process of 241Am-Be neutron source logging, and discuss neutron source management and protective measures for operators in well logging. Methods Through on-site observation and measurement of 241Am-Be neutron source logging in a company, we obtained the surface γ dose rate and neutron dose rate of the neutron source, as well as the operating time and distance of various processes including source taking, transfer, and loading, calculated the radiation dose to operators in various processes, and analyzed the source and proportion of the personal effective dose to operators. Results The effective doses of neutron irradiation and γ irradiation were 94.17 μSv and 2.72 μSv, respectively, for the combined processes of source tank inspection, transfer, and detection; 36.66 μSv and 24.08 μSv, respectively, for source loading and unloading; and 130.83 μSv and 26.80 μSv, respectively, for the whole neutron source logging process. The total annual effective dose of neutron source logging was 15.78 mSv, as estimated by logging 100 times per year. Conclusion In the process of 241Am-Be neutron source logging in the company, the effective dose to operators mainly arises from neutron irradiation. Therefore, it is necessary to strengthen neutron source management and take effective protective measures against neutron radiation.
