Application of boron-containing polyethylene as maze wall lining shielding for a 10 MV medical accelerator room
10.13491/j.issn.1004-714X.2025.01.012
- VernacularTitle:含硼聚乙烯作为迷路墙内衬材料在10 MV医用加速器机房屏蔽防护中应用案例
- Author:
Yajing SONG
1
;
Jing SU
2
;
Shihua TAO
1
;
Zechen FENG
3
Author Information
1. Beijing Betalab Technology Detection Co., LTD, Beijing 100013 China.
2. Institute of Radiation Medicine, Shandong Academy of Medical Sciences, Jinan 250062 China.
3. Beijing Center for Disease Control and Prevention, Beijing 100013 China.
- Publication Type:OriginalArticles
- Keywords:
Accelerator;
Boron-containing polyethylene;
Neutrons;
Shielding
- From:
Chinese Journal of Radiological Health
2025;34(1):73-76
- CountryChina
- Language:Chinese
-
Abstract:
Objective To evaluate the ambient dose equivalent rates of photons and neutrons inside and outside the door of a 10 MV accelerator room, and to report the shielding effect of boron-containing polyethylene as maze wall lining. Methods The ambient dose equivalent rates of photons and neutrons inside and outside the door of an accelerator room were taken as the research subject. The Kersey, Falcão, and modified Kersey methods were used to calculate the ambient dose equivalent rates of neutrons and neutron capture gamma rays inside and outside the door of the room before and after renovation. Measurements were made using an X-ray/γ-ray dose rate instrument and a neutron ambient dose equivalent rate meter. Calculated and measured results were compared. Results Before renovation, the measured neutron dose rate inside the door was 409 μSv/h, while the calculated values were 323 μSv/h (Kersey method), 428 μSv/h (Falcão method), and 219 μSv/h (modified Kersey method). The Falcão method yielded a value closest to the measured value, while the Kersey and the modified Kersey methods underestimated the value by 21% and 46%, respectively. After the installation of boron-containing polyethylene plates, the measured neutron dose rate inside the door was 190 μSv/h, with a 54% reduction. The neutron and photon ambient dose equivalent rates outside the door were 5.8 μSv/h and 6.0 μSv/h, respectively, before renovation, and 0.14 μSv/h and 1.6 μSv/h, respectively, after renovation. Conclusion For a 10 MV accelerator room, neutron shielding and protection measurements are necessary, especially for rooms with short mazes. The Falcão method provides the best estimate of neutron dose rates inside and outside the door. Using boron-containing polyethylene plates as maze wall lining is an economical and effective shielding method.
