Table of Content

20 August 2025 Volume 45 Issue 4

  

Management

Management practice and consideration of historical exposure dose for itinerant workers in nuclear power plants

LUN Zhenming, YU Enjian, JIANG Zhao, ZHANG Hongxu

RADIATION PROTECTION BULLETIN. 2025, 45(4):  1-6. 

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With the development of China′s nuclear power industry, the number and frequency of workers moving among nuclear power plants are increasing. Therefore there could be more and more problems and hidden troubles in the declaration process of historical radiation dose of these workers in each nuclear power plant, which may have a negative impact on the continuity of individual dose at different power plants and the control of individual dose limits. Based on the investigation of the current situation of China′s nuclear power industry and the domestic and foreign practice, suggestion on setting up a personal dose networking center is put forward, and its necessity, feasibility and legitimacy are analyzed from the industry level.

Investigation on long-term monitoring and maintanence of decommissioned uranium mining facilities

AN Jimin, ZHU Jie, XIE Rongrong, LI Feng

RADIATION PROTECTION BULLETIN. 2025, 45(4):  7-12. 

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Implementing long-term monitoring and maintanence of decommissioned uranium mining facilities is a crucial measure and important support for ensuring environmental safety and safeguarding public health. Taking monitoring and maintanence of decommissioned uranium mining facilities as the investigation object, this paper investigates the current status of uranium mining facility monitoring and maintanence at home and abroad. This work analyzes the main existing problems such as the mutual influence between public activities and monitoring work, the incompatibility between the functions and responsibilities of monitoring agencies, as well as the imperfection of regulatory standards. Finally, this paper puts forward reasonable suggestions for the establishment of regulations, standards, and evaluation systems.

Ariticles

Design and testing of a standby replacement device for automatic air monitoring stations in radiation environment

WANG Liang, GUO Chunyan, YU Tengyang, BI Chaowen, ZONG Zhilong, XU Hailiang, YANG Qiang

RADIATION PROTECTION BULLETIN. 2025, 45(4):  13-20. 

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The standby replacement device plays a vital role in ensuring continuous and stable operation of automatic air monitoring stations in radiation environment, and addressing the issue of discontinuous monitoring data caused by station disconnections. The hardware design of the device includes a data acquisition system and communication system, supporting conventional serial ports, RJ45 Ethernet ports, USB, and other interfaces. The software modules comprise three components: data acquisition, data reporting, and data re-transmission. Data are encrypted and uploaded to the national data center and provincial data centers via a VPN (Virtual Private Network). Dual-mode communication ("Wired Broadband" and "4G/5G Wireless Network") is employed for communication with provincial center servers. The reporting communication adopts the TCP protocol via sockets. A mechanism for re-transmitting missed data is established within the data reporting and data re-transmission modules to ensure the integrity of reported data. Tests conducted in Mohe (Heilongjiang), Shigatse (Tibet), and Sanya (Hainan) demonstrate that the standby replacement device operates stably and reliably, effectively enabling buckup data re-transmission for radiation environmental air monitoring stations.

Investigation and analysis of radiation dose for pediatric CT examinees in a hospitals

YUE Lei, YAN Qingqian, YANG Sheng, QI Jie

RADIATION PROTECTION BULLETIN. 2025, 45(4):  21-26. 

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This study investigated the radiation dose distribution of children′s CT scans in a hospital in Nanjing, with the aim of understanding the radiation dose levels of pediatric subjects in the hospital′s CT examinations and providing a basis for exploring and establishing the diagnostic reference level (DRL) for children′s CT examinations in this hospital. This study retrospectively collected basic information and CT imaging data of pediatric subjects who underwent CT diagnosis at the hospital from 2020 to 2024. Three examination sites, namely the head, chest, and abdomen, were collected, and the subjects were divided into four age groups according to age<1, 1~<5, 5~<10, and 10~≤ 15 years old. The differences in dose distribution between different age groups in the same site were analyzed; At the same time, this article used the median(P₅₀) of CTDI_vol and DLP as dose reference levels to compare with other regions. The median values(P₅₀) of CTDI_vol and DLP at the corresponding examination sites in the four age groups of<1~<5, 5~<10, 10~≤ 15 years old were as follows: head: 4.3, 6.9, 7.4, 8.2 mGy and 78.9, 143.3, 153.5, 173.0 mGy·cm; Chest: 1.7, 2.1, 3.4, 4.1 mGy and 32.9, 50.9, 90.2, 131.7 mGy·cm; Abdomen: 2.2, 3.8, 4.2, 5.7 mGy and 55.8, 137.5, 175.0, 290.1 mGy·cm. Among them, there were statistically significant differences in CTDI_vol and DLP between different age groups of the same body part (head, chest, and abdomen, CTDI_vol:χ²=173.47,199.91,158.91; DLP:χ²=186.73,265.97,210.99,P<0.001). The P₅₀ digits of CTDI_vol and DLP in various body parts of pediatric patients in this hospital are generally lower than the national level, However, there are still some examinees whose CTDI_vol and DLP are higher than DRL cited in GBZ 130—2020. Therefore, it is necessary to further optimize the CT scanning program.

Experiences

Comparison of enrichment and separation methods for uranium in environment water samples

LIANG Guoshuai, CHEN Baidi, HE Gaopeng

RADIATION PROTECTION BULLETIN. 2025, 45(4):  27-31. 

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To explore a stable, fast, and suitable method for uranium enrichment and separation from environment water samples, this study used N-235 extraction, TBP extraction chromatography, and ion exchange methods to enrich and separate uranium from freshwater and seawater samples. The experimental procedures and effects were compared. The results showed that: the recovery rates of uranium from environment seawater and freshwater samples using the N-235 extraction method were 73.3%±5.6% and 69.5%±8.2%; while the recovery rates using TBP extraction chromatography method were 88.6%±4.1% and 58.9%±5.0%; the recovery rates of uranium using ion exchange method were 74.9%±10.1% and 57.7%±7.6%. With consideration of the recovery rates, experiment time and waste recovery, etc, it was indicated that the TBP extraction chromatography method was better for enriching and separating uranium from environment water samples.

Habitability analysis and improvement of the main control room of EPR unit in a nuclear power plant

WEI Peng, LI Xiaochen, YANG Zhichao, ZHANG Wei, WU Tao, ZHANG Yuan, GAO Linfeng, LI Yongguo, LI Jian, LIU Tao, ZHANG Chongwen

RADIATION PROTECTION BULLETIN. 2025, 45(4):  32-37. 

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On the background of general attention to the air in-leakage experiment and habitability for main control rooms of nuclear power plants, an in-leakage tracer gas experiment for a third-generation nuclear power plant is introduced. Experimental results show that the unfiltered air in-leakage of the main control room is smaller than some other nuclear power plants with no design requirements, but there is still room for improvement. Measures of real practicability originated from the analysis of the causes of unfiltered air in-leakage are suggested.

Analysis on examination results of radiation workers′ occupational health in Taizhou City from 2022 to 2024

LI Tiantian, FANG Jiayang, GENG Zi'ang, WANG Xiaoli, MA Fuqiu

RADIATION PROTECTION BULLETIN. 2025, 45(4):  38-43. 

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By analyzing the abnormal rate of occupational health examination results and further understanding their health status of radiation workers in Taizhou City, in order to provide a basis for health monitoring and risk assessment of radiation workers. This study selects data from 4 351 radiation workers in Taizhou City from October 2022 to September 2024 for investigation, the impact of different genders, working years, job types, and ages on the health of radiation workers are compared and analyzed. The results show that the abnormal detection rate of absolute lymphocyte count increases with working years (χ²=11.602, P<0.05). The abnormal rates of white blood cell count (7.3%) and FT3 (2.7%) in the nuclear fuel cycle group are higher than those in the medical application group and industrial application group (χ²=19.440, 22.370, both P<0.05). The abnormal rate of lymphocyte percentage in the industrial application group (6.9%) is higher than that in the nuclear fuel cycle group and medical application group (χ²=7.047, P<0.05). The abnormal detection rates of absolute lymphocyte count and FT3 in male radiation workers are higher than those in female workers (6.4%>3.2%, 1.7%>0.5%, χ²=18.467, 10.799, both P<0.05), while the abnormal detection rates of FT4 and TSH in female radiation workers are higher than those in male workers (1.0%>0.2%, 3.6%>1.6%, χ²=12.207, 15.582, P<0.05). Long-term low-dose ionizing radiation exposure has a certain impact on the occupational health of radiation workers in Taizhou City. Therefore, it is necessary to further strengthen the awareness of radiation protection among radiation workers to further protect their occupational health.