Table of Content

20 August 2026 Volume 46 Issue 4

  

Reports

Study on scaling factors of difficult-to-measure radionuclides ⁵⁵Fe, ⁶³Ni and ⁹⁰Sr in radioactive solid wastes from domestic nuclear power plants

YAO Yongjin, SHEN Enwei, YU Bo, JIANG Jing, QUE Ji, ZHANG Qingzhao, LEI Qiang

RADIATION PROTECTION BULLETIN. 2026, 46(4):  1-7. 

Abstract ( 16 )   PDF (1136KB) ( 9 )  

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This study took radioactive wastes from four domestic nuclear power plants as analytical objects, including spent resin, concentrate (dry salt powder), water filters, and activated carbon. Representative sampling and analysis were performed on waste samples from these plants to obtain the activity concentrations of the difficult-to-measure radionuclides (⁵⁵Fe, ⁶³Ni and ⁹⁰Sr) and key nuclides in the samples. The scaling factors of ⁵⁵Fe, ⁶³Ni and ⁹⁰Sr in different types of solid radioactive wastes from nuclear power plants were determined using the geometric mean method. Meanwhile, a comparison was made with the scaling factors of difficult-to-measure radionuclides from foreign nuclear power plants. Significant differences were found in most scaling factors. It is ultimately confirmed that domestic nuclear power plants are not suitable for directly adopting the scaling factors for difficult-to-measure radionuclides established by foreign counterparts with the same type of nuclear power plants. Instead, it is necessary to carry out independent waste sampling and measurement to determine site-specific scaling factors for difficult-to-measure radionuclides.

Study on the measurement method of total alpha and total beta radioactivityin solid soil and sediments

CAO Pengtao, ZHANG Yongtao, WANG Lihua, WANG Wenjun, ZHANG Liang

RADIATION PROTECTION BULLETIN. 2026, 46(4):  8-12. 

Abstract ( 16 )   PDF (761KB) ( 10 )  

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To rapidly assess the radioactivity levels of solid samples such as soil and sediments, the determination of gross alpha and gross beta radioactivity can be employed as a rapid screening technique to preliminarily evaluate the contamination level of samples and provide assessment support for regulatory authorities.In this paper, the particle size for sample disk loading and the sample loading amount were optimized, and 100-mesh sifting together with a mass thickness of 0.015 g/cm² were determined as the parameters for optimal efficiency.The thick source method was adopted for the measurement of gross alpha and gross beta radioactivity, and verification tests were conducted across different laboratories using samples of different matrices at three activity concentration levels (high, medium and low).The results demonstrate that the minimum detectable activities of gross alpha and gross beta satisfy the requirements for environmental sample analysis; the relative standard deviation of the measurements is less than 20%, and the spiked recovery ranges from 70% to 130%, which can guarantee the comparability and traceability of the measurement results.

Study on pretreatment methods for radioactive organic deposits

WANG Wenlong

RADIATION PROTECTION BULLETIN. 2026, 46(4):  13-17. 

Abstract ( 15 )   PDF (940KB) ( 8 )  

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Through high-temperature nuclide loss tests, mixed dissolution tests and interference influence studies, a suitable pretreatment method for radioactive organic deposits was formed. The high-temperature carbonization + mixed acid treatment process has a mild reaction without liquid splashing, reducing the probability of aerosol generation. The recovery rates of the nuclides (⁹⁰Sr, ¹³⁷Cs, ²⁴¹Am, ²³⁹Pu) are all greater than 91%. The actual samples can be completely converted into aqueous solutions after being treated by this method. The relative standard deviations of the measurement results of the nuclides are all less than 9%, providing an accurate data basis for the subsequent treatment and disposal of high-level radioactive organic deposits.

The distribution characteristics of ⁹⁰Sr in the seawater of western Guangdong

CHEN Fuliang, LIANG Guoshuai, ZHU Shenhe

RADIATION PROTECTION BULLETIN. 2026, 46(4):  18-22. 

Abstract ( 15 )   PDF (2321KB) ( 9 )  

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A five-year monitoring program was conducted for the radionuclide ⁹⁰Sr in the seawater of the coastal areas of three prefecture-level cities in western Guangdong, namely Zhanjiang, Maoming and Yangjiang, as well as the sea area adjacent to the Yangjiang Nuclear Power Base. The distribution characteristics of this radionuclide were analyzed. The monitoring results show that the activity concentration of ⁹⁰Sr in seawater of the three coastal cities in western Guangdong ranged from 0.25 to 0.98 mBq/L, while that in the sea area around the Yangjiang Nuclear Power Base ranged from <0.15 to 1.2 mBq/L. Spatially, there was no significant difference in the activity concentration of ⁹⁰Sr (P>0.05). Temporally, no significant trend was observed in the activity concentration of ⁹⁰Sr in seawater over the past five years. The activity concentration of ⁹⁰Sr in seawater of western Guangdong was lower than the limit (4 Bq/L) specified in the Sea Water Quality Standard (GB 3097—1997), and showed no significant difference from that in coastal seawater across China.

Analysis of the surface emission rate response of common α/β surface contaminationmonitors to ¹⁴C β rays

LI Xiaoshuang, LU Xiaojun, SONG Jiaban

RADIATION PROTECTION BULLETIN. 2026, 46(4):  23-28. 

Abstract ( 18 )   PDF (1985KB) ( 13 )  

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To investigate the differences in detection performance and the underlying influence mechanisms of various types of α/β surface contamination monitors for low-energy beta rays, this paper selects a ¹⁴C planar source (with a maximum beta energy of 156 keV) as a typical research subject and systematically conducts an experimental study on surface emission response characteristics using multiple commercial monitors equipped with scintillation detectors, Geiger-Müller (G-M) counters, and proportional counters. The results indicate that different instrument types exhibit varying responses to low-energy beta rays from ¹⁴C. Specifically, the scintillation detectors show a wide response range from 0.2% to 21.1%, the G-M counters show a response range of 8.3% to 12.2%, and the proportional counter yields a response of 7.9%. However, for windows made of the same material, the mass thickness is negatively correlated with the instrument′s response to ¹⁴C beta rays, while the penetration rate, which is determined by the mass thickness, is positively correlated with the response value. These findings can provide important technical references for the surface contamination monitoring of ¹⁴C, and also hold practical value for the domestic development of surface contamination monitors, performance optimization, and user equipment selection.

Investigation and analysis of the current status of radiation hygiene managementof X-ray bone densitometer in Yancheng City, China

CHEN Yuzhong, ZHOU Xian, WANG Lu, ZHU Yu, ZHANG Yifei

RADIATION PROTECTION BULLETIN. 2026, 46(4):  29-33. 

Abstract ( 15 )   PDF (702KB) ( 6 )  

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Objective To investigate and analyze the current status of radiation hygiene management of X-ray bone densitometer in Yancheng City, China, identify weaknesses in management, promote the safe and orderly operation of radiological diagnostics, and provide a basis for relevant departments to strengthen radiation hygiene management. Methods A comprehensive survey was conducted on the equipment usage and radiation hygiene management in all institutions performing. X-ray bone densitometer in Yancheng. Radiation levels were also monitored. Results A total of 29 medical institutions in the city performed X-ray bone densitometer examinations, equipped with 29 examination devices and 192 radiation staff. Among these institutions, 27 had their bone densitometer examination projects approved by health authorities, representing a licensing rate of 93.1%. The rates for occupational health examinations, radiation protection knowledge training, and personal dose monitoring for radiation staff were all 100%.The qualified rate of protection test indicators in the operating room of the compartment was 100%。The provision rates of protective equipment for examinees, operational status indicators, and powered ventilation systems were 96.6%, 96.0%, and 96.0%, respectively. Conclusions The overall status of radiation hygiene management for X-ray bone densitometer in Yancheng is relatively good, but there are still some shortcomings and deficiencies. It is necessary to strengthen the construction of workplace shielding and supporting protective facilities, and to further standardize X-ray bone densitometer practices to safeguard the health and safety of radiation staff, examinees, and the public.

Analysis of chromosome aberrations in isolated human peripheral blood irradiated by γ rays andestablishment and verification of dose-effect curves

LONG Gaoqun, JIANG Hong, ZHANG Chengsi, TIAN Zhujuan, LI Yuanhang

RADIATION PROTECTION BULLETIN. 2026, 46(4):  34-37. 

Abstract ( 16 )   PDF (704KB) ( 2 )  

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Peripheral venous blood samples were collected from four healthy individuals and irradiated with 0.00,0.50,0.75,1.00,2.00,3.00,4.00,5.00 Gy ⁶⁰Co γ rays in vitro.Chromosome specimens were routinely cultured,harvested,and prepared. After manual analysis and confirmation,a dose-response curve was fitted to the double centromere(dic)and centromere ring(r),and the curve was validated to establish a laboratory biological dose estimation effect curve. Based on the manual analysis and confirmation of the dic+r number,the CABAS 2 software was used to fit the curve as Y=0.074 1D²+0.047 2D+0.809 0×10^-3,R²=0.99,Substitute the dic+r distortion rate of the 2021 and 2023 assessment samples into the dose-response curve for biological dose estimation.If the difference between the estimated dose and the irradiation dose is within 20%,the result is judged as qualified. The dose-response curve established in this laboratory has been validated through experiments,confirming the feasibility of using it for biological dose estimation.

Analysis of personal dose monitoring results for radiation workers in a nuclear-specialized tertiary general hospital in Sichuan Province from 2021 to 2024

YAN Liting, TANG Ying, SHAO Jichun

RADIATION PROTECTION BULLETIN. 2026, 46(4):  38-42. 

Abstract ( 18 )   PDF (708KB) ( 13 )  

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Objective To analyze and understand the individual dose of occupational external exposure among medical radiation workers in a nuclear-specialized tertiary Grade A general hospital in Chengdu, Sichuan Province, and to evaluate the effectiveness of its protection and related management. Methods Data on the annual individual exposure doses of all radiation workers in this hospital from 2021 to 2024 were collected and organized. A retrospective analysis of the collected data was conducted using statistical analysis software (SPSS). Results The median of annual effective dose for workers in this hospital from 2021 to 2024 was 0.34 mSv. The highest dose was observed in 2023 (0.38 mSv), and the lowest in 2024 (0.28 mSv), with a statistically significant difference (P<0.01). Comparison among different job categories showed that the sample number for dental radiology was too small to be included in the discussion. Radiotherapy workers received the lowest annual effective dose (0.24 mSv), while nuclear medicine workers received a dose of 0.44 mSv, with a statistically significant difference (P<0.01). There was no statistically significant difference in the annual effective dose between male and female workers (P>0.05). Conclusions The current status of radiation protection in this hospital is generally safe and effectively safeguards the occupational health of radiation workers. It is recommended to continuously monitor the individual doses and occupational health examination results of medical workers in different radiation job categories, adhering to the principle of optimizing protection.

Experiences

A case study on the source jam incident at an irradiation center

CHANG Yanfeng, YANG Dejun, LIU Yuxia

RADIATION PROTECTION BULLETIN. 2026, 46(4):  43-46. 

Abstract ( 19 )   PDF (1300KB) ( 9 )  

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The occurrence process, emergency response, and troubleshooting process of the source jam incident that took place at an irradiation center in Shenyang, Liaoning Province in February 2025 were introduced. the causes of the incident were analyzed, and the lessons learned were summarized.