Table of Content

20 October 2025 Volume 45 Issue 5

  

Expert Forum

Reevaluation of radiological medicine

BAI Guang

RADIATION PROTECTION BULLETIN. 2025, 45(5):  1-7. 

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This paper reviews and analyzes the medical surveillance and clinical radiological practices of radiation workers in China. Based on the analysis, this paper suggests abandoning the radiological medicine model focused on medical surveillance. Taking ICRP Publication 118 framework as reference, the ending of the "chronic radiation sickness" definition from former Soviet Union, which is still used in China, is called for. This paper also proposes establishing a new radiological medicine model based on dose-effect relationships and defining and developing China's radiological medicine across health physics, medical treatment, and ionizing radiation-related medicine. Radiological medicine in the new era should extend beyond occupational medicine to embrace diversified development.

Ariticles

Investigation of gross α and gross β levels in ambient drinking water around Daya Bay nuclear power station (2021-2023)

WU Yini

RADIATION PROTECTION BULLETIN. 2025, 45(5):  8-12. 

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To further understand the impact of nuclear power plant operation on the total radioactivity levels in surrounding drinking water, gross α and gross β in drinking water samples were collected and analyzed near Daya Bay nuclear power station from 2021 to 2023. Following the technical specifications for radiation environmental monitoring, quarterly monitoring was conducted at three sampling sites (Urban Inns, Pengcheng and Shenzhen city) and one control site (Fogang). The measured activity concentrations ranged from 0.004 to 0.033 Bq/L for gross α and 0.020 to 0.150 Bq/L for gross β. These results demonstrate that the radioactivity levels in drinking water around Daya Bay nuclear power station were all below the guidance limits specified in the current standards for drinking water quality.

Experiences

Research on the optimization of nuclear emergency notification reports and communication methods in nuclear power plants

MA Wen, GOU Quanlu, WU Rong, YAN Lili, WU Wenchao

RADIATION PROTECTION BULLETIN. 2025, 45(5):  13-19. 

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During emergency response to a nuclear accident in a nuclear power plant, the timeliness and accuracy of nuclear emergency notification reports and the reliability of communication methods are crucial for nuclear emergency organizations at all tiers to implement the nuclear emergency work policy of "unified command and vigorous coordination". High-quality development of the nuclear power industry has put forward higher requirements for work related to nuclear emergency notifications and reports. The rapid upgrade of emergency communication technology has provided technical support for the safe, reliable and timely completion of nuclear emergency notifications and reports. On the basis of sorting out current relevant regulations, guidelines, and standards, and by conducting surveys on domestic representative nuclear power plants, focucing at the common and difficult issues existing in the industry, suggestions for optimization and improvement in terms of diversification of communication means were put forward, from hierarchical management of emergency communication system equipment, standardization of nuclear emergency notification reports, and rapid data acquisition. These suggestions could lay a more solid foundation for ensuring the effective operation of the three-tier nuclear emergency management system, controlling and mitigating the consequences of nuclear accidents.

A method for estimating derived air concentration of aerosol by using wiping sampling in nuclear power plants and its application in high flow rate air sampling

REN Xueming, SONG Yushou, LI Wei, WANG Tiancheng, ZHU Shuiping, WU Genqiu, MA Qiang

RADIATION PROTECTION BULLETIN. 2025, 45(5):  20-27. 

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A simpling method is proposed to estimate the derived air concentration (DAC) of aerosols in nuclear power plants through wiping sampling. This method considers the correction of difficult to measure nuclide 63Ni and the correction of response coefficients between different areas of measuring instruments, wiping sampling paper, and high flow rate air sampling filter paper. Based on the measurement and analysis of the average half-life of radon and its daughters in the deposition part of high flow rate air sampling filter paper, a correction method for the measurement results of high flow rate air sampling is proposed. The main conclusions are as follows: (1) The proportion of representative nuclides measured by wiping samplings is relatively consistent with that measured by actual air sampling; (2) The correction of difficult to measure nuclide 63Ni has a minor impact on the overall results, ranging from 1% to 4%; (3) A typical mixed DAC ranges from 1.62×10³ Bq/m³ to 3.02×10³ Bq/m³, which has certain reference value in similar nuclear power plants; (4) A mixed DAC on air sampling filter paper for a nuclear power plant is relate to 14-66 s^-1 measured using 6150AD5+AD17 and CF-901-DIGITAL/230 under given measurement conditions; (5) The average half-life of radon and its daughters varies from 6 minutes to 12 minutes under the set sampling time and sampling flow rate. Other nuclear power plants can refer to the above mentioned methods to measure the typical mixed DAC and the typical relationship between aerosol concentration values and surface contamination values of their nuclear power plants, in order to guide high flow rate air sampling and set aerosol contamination determination thresholds.

Discussion on the application of drone aerial surveyin radiation environment monitoring

HUANG Shiyao

RADIATION PROTECTION BULLETIN. 2025, 45(5):  28-34. 

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In order to meet the requirements of radiation environment monitoring capabilities under new situation, comprehensive monitoring of land, sea, and air has become an inevitable trend. Drone aerial surveying has the characteristics of high speed, efficiency, and wide coverage, which could play an important role in radiation environment monitoring, especially in emergency monitoring of nuclear and radiation accidents. This article is based on an example of aerial survey of radiation environment around nuclear facilities, and compares it with data from fixed monitoring sub-stations and ground survey data to verify the reliability of aerial survey data and the diversity of monitoring methods. The aim is to provide reference for regulatory authorities to promote the modernization of nuclear safety supervision system and supervision capabilities.

Establishment of standard equipment for environmental level multi-source gamma ray air kerma

CHEN Shuangqiang, WEI Yingjing, LI Yin, FANG Dengfu, TANG Zhihui, FENG Mei

RADIATION PROTECTION BULLETIN. 2025, 45(5):  35-40. 

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In order to carry out the traceability and transmission of the value of radioactive environmental monitoring instruments, according to the characteristics and generation methods of X and γ reference radiation in GB/T 12162.1—2000 and the calibration specification of JJF 1733—2018, the environmental level multi-source γ-ray kerma standard device was established. The experimental results show that: the air kerma rate range of the standard equipment for multi-source γ-ray air kerma at environmental level is (1.0×10^-1-3×10²) μGy/h; the radiation field with non-uniformity of less than 5% at 1 m is ø 300 mm; and the inverse square law is consistent within 5.0% in the range of 1 m-5 m from radioactive source. The stability and reproducibility of the device measured by standard ionization chamber were 1.7% and 0.5%. The relative extended uncertainty of the device is 3.0% (k=2) by evaluating the uncertainty component of the measurement results. The measurement results show that the performance indicators of the environmental level multi-source γ-ray air kerma standard device meet the requirements of the calibration of the environmental level dose measurement instrument.

Reports

Study on the problems and solutions in emergency preparedness for radiation accidents in nuclear technology utilization institutions

ZHANG Jing, YOU Qi, LIU Yanbo, HE Feili, FAN Hong, LIN Quanyi

RADIATION PROTECTION BULLETIN. 2025, 45(5):  41-45. 

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Through multiple approaches including data collection, field surveys and interviews, an investigation was conducted on radiation accident emergency preparedness of nuclear technology utilization institutions in a city. The findings indicate that some institutions exhibit weak awareness of radiation safety and emergency management, lack of operability in their emergency plans, as well as insufficient emergency supplies and professional personnel. Based on the principle of graded approach, differentiated improvement measures need to be formulated. This paper analyzes the issues from perspectives such as safety management system, personnel training mechanisms and building standardization system, and proposes corresponding improvement strategies.