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  • Original Articles
    YI Junxuan, DONG Xiaodan, XUE Wenxiang, GAO Shuying, XUE Naiwen, JIN Shunzi
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    Objective To investigate GATA3 expression and the regulatory mechanism of m6A modification in the response of alveolar epithelial cells to radiation, and to provide a new therapeutic target for radiation-induced lung injury based on its pathogenesis. Methods Human lung epithelial cell line (A549) and mouse lung epithelial cell line (MLE-12) were exposed to X-ray irradiation with a single dose of 10 Gy (dose rate 1 Gy/min) and 6 Gy (dose rate 0.75 Gy/min), respectively. The expression of VIRMA gene (RNA methylase) was inhibited by lipofection of A549 cells and MLE-12 cells with shRNA-VIRMA plasmid and siRNA-VIRMA interfering fragment, respectively. Quantification of m6A RNA methylation was performed by colorimetry. Changes in the expression of mRNAs of VIRMA, GATA3, and epithelial-mesenchymal transition (EMT) markers in irradiated A549 and MLE-12 cells were determined by qRT-PCR. Changes in the expression of VIRMA, GATA3, and EMT marker proteins in irradiated A549 and MLE-12 cells were determined by Western blot. Results Radiation up-regulated the expression of methylase VIRMA in A549 and MLE-12 cells, which in turn enhanced the m6A of total RNA and the expression of GATA3 gene and protein, resulting in EMT. Furthermore, in A549 and MLE-12 cells, interference of the VIRMA gene significantly reduced the expression of GATA3 gene and protein and the expression of EMT-related molecules. Conclusion Radiation induces m6A modification in alveolar epithelial cells, which up-regulates the expression of GATA3 gene and induces EMT, thus playing an important role in the process of radiation-induced lung injury.
  • Original Articles
    MA Xiangjie, HE Zhijian, YUAN Jilong, JIANG Qinghuan, LI Mingsheng, WEI Xiao, YANG Yuze, CHENG Jinsheng
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    Objective To explore the feasibility of quartz glass for radiotherapy dosimetry through the experimental study of the thermoluminescence characteristics of synthetic quartz glass. Methods The thermoluminescence glow curves of quartz glass under different annealing conditions were analyzed, the thermoluminescence characteristics of quartz glass were studied, and the measurement parameters were optimized. Using the Co-60 reference radiation field in the National Secondary Standard Dosimetry Laboratory, the quartz glass samples under different annealing conditions were irradiated following the dose levels of radiotherapy, i.e., 0.5, 1.0, 2.0, 4.0, 6.0, 8.0, and 10.0 Gy, respectively. According to the relationship between the absorbed dose of quartz glass and the relative thermoluminescence signal intensity, the linearity and dispersion of the dose response of quartz glass were obtained, and the feasibility of quartz glass for radiotherapy dosimetry was analyzed. Results The linear correlation coefficient of dose response of quartz glass under annealing condition of 430℃ for 10 min was 0.9984, and the dose response dispersion was 0.97% at the absorbed dose of 2 Gy. The linear correlation coefficient of dose response of quartz glass under annealing condition of 600℃ for 1 h was 0.9911, and the dose response dispersion was 1.4% at the absorbed dose of 2 Gy. Conclusion Preliminary results suggest that quartz glass with annealing condition of 430℃ for 10 min has the potential to be used for radiotherapy dosimetry.
  • Original Articles
    LIU Jie, SUN Jingzhi, FENG Jiawu, ZHOU Xuan, ZHANG Li, BI Meng
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    Objective To analyze the results of national personal dose monitoring intercomparison and assessment of Hubei Provincial Hospital for Occupational Disease in 2016—2021, to investigate the influencing factors for monitoring results, and to improve the ability of personal dose monitoring. Methods The assessment was completed according to the requirements of The National Comparison Scheme for Individual Dose Monitoring Ability and Testing Criteria of Personnel Dosimetry Performance for External Exposure (GBZ 207—2016). Results The assessment results were qualified in 2016—2017 and 2020 and excellent in 2018—2019 and 2021. Conclusion The ability of personal dose monitoring in our laboratory has been continuously improved. The monitoring results are accurate and the data processing is standardized, which meet the requirements of relevant standards for personal external exposure dose monitoring.
  • Original Articles
    WANG Jing, GAO Yingping, MEI Dan, MA Kui, MEI Liangying, FANG Xiaoguang
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    Objective To analyze the problems and solutions in the diagnosis of a patient with occupational radiogenic neoplasms. Methods The dose conversion method was selected in dose estimation. Personal dose equivalent, skin absorbed dose, and reported detection data were converted into red bone marrow absorbed dose. The upper 95% confidence limit of the probability of causation (PC 95%) was calculated. Results The PC 95% of cancer due to radiation in the worker was 66.38%, which suggested occupational radiogenic neoplasms. Personal dose data were missing in dose estimation. The current dose estimation standard lacked bedside radiography and CT operation type, and the dose conversion formula was not perfect. Conclusion In the judgment of occupational radiogenic neoplasms, the estimated dose showed uncertainty. There is an urgent need to formulate and promulgate dose estimation standards that are operational and in line with the current development of radiological diagnosis and treatment technology and equipment.
  • Original Articles
    XIONG Qiang, GE Xiao, YAN Linlin, CHEN Fei, ZHANG Zhen
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    Objective To improve the determination of gross α and gross β radioactivity in soil, establish a fast and accurate method for soil radioactivity analysis, and provide a basis for establishing standard methods for analysis of gross α and gross β radioactivity in soil. Methods Using the method of soil nuclide extraction and the sample preparation method for low background α/β counter, an extraction-enrichment method was established to monitor the radioactivity of gross α and gross β in soil. Meanwhile, the radioactivity of gross α and gross β in the same soil samples was determined using the direct paving method. An optimal method of monitoring gross α and gross β radioactivity in soil was put forward by comparing the advantages and disadvantages of the two methods. Results With the direct paving method, the radioactivity of gross α and gross β in soil was 0.47 Bq/g and 0.85 Bq/g, respectively; and the minimum detection limit was 0.04 Bq/g and 0.02 Bq/g, respectively. With the extraction-enrichment method, the radioactivity of gross α and gross β in soil was 0.32 Bq/g and 0.29 Bq/g, and the minimum detection limit was 0.02 Bq/g and 0.01 Bq/g. Conclusion Comparison of the two detection methods showed that the direct paving method is more accurate and easier to operate, while the extraction-enrichment method is complex in operation and has relatively large system error but provides a lower minimum detection limit.
  • Original Articles
    SONG Ying, LIU Hui
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    Objective To determine the responses of radioactivity meter at different positions in the vertical direction of the ionization chamber by measuring different radioactive sources. Methods The radiation of cesium-137, cobalt-60, and americium-241 nuclides was measured at different positions in the vertical direction of the ionization chamber with commonly used clinical radioactivity meters. The measured values were fitted to obtain three trend lines. The maximum deviation of the measured values was estimated according to the trend line, and the deviation was estimated at different syringe needle heights. Results According to the trend lines, the maximum deviation of the radioactivity meter CRC-55tR in measuring cesium-137, cobalt-60, and americium-241 nuclides was 5.15%, 5.98%, and 6.25% respectively. The radioactivity meter RM-905a was used to measure three nuclides at different syringe needle heights, and the maximum deviations were −4.33%, −9.9%, and −12.65%, respectively. Conclusion The three nuclides showed different change patterns in measurement with CRC-55tR and RM-905a but similar change patterns in measurement with the same radioactivity meter. The values measured with the same radioactivity meter showed significant deviations at different positions in the vertical direction of the ionization chamber. It is recommended to make position correction for commonly used nuclides. Reducing measurement error and improving measurement accuracy of nuclides are of great significance for radiation protection.
  • Original Articles
    ZHANG Wei, XIA Chundong, ZHANG Xianpeng, LIU Yi, WANG Xinyun
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    Objective To analyze the radionuclide levels in food and the committed effective dose due to food intake in residents around the Shidaowan Nuclear Power Plant (SNPP). Methods Daily food samples were collected within 30 km radius around the nuclear power plant in 2019—2022. The radioactivity levels before and after the operation of SNPP were determined. The data were combined with the dietary consumption of residents in Shandong province, China to estimate the committed effective dose. Results The radionuclides 238U, 232Th, 226Ra, and 40K in food were at normal background levels, and the average radioactivity was (0.062 ± 0.004), (0.121 ± 0.007), (0.162 ± 0.010), and (92.4 ± 5.5) Bq/kg fresh weight. Trace 137Cs and 90Sr were detected in some food samples and the average radioactivity was (0.047 ± 0.003) and (0.193 ± 0.200) Bq/kg fresh weight. The levels of radionuclides did not increase after the operation of SNPP compared with that before operation. The estimated committed effective dose in residents due to food intake was 0.205 mSv. Conclusion The radioactivity of food in the area around SNPP shows no difference before and after operation, and the dose burden is low in local residents.
  • Original Articles
    WU Jianhua, PANG Hongchao, LUO Zhiping, LIU Yang, LI Xinglong, YUAN Guojun
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    Objective To develop a simplified phantom for the calibration of whole-body counters. Methods A simplified phantom design method for the calibration of whole-body counters was established based on the process and method of calibrating whole-body counters. By using the established method and Monte Carlo method, a simplified phantom including the total body, thyroid, lungs, and gastrointestinal tract was designed to calibrate the ORTEC-Stand FAST II whole-body counter. The simplified phantom was compared with the BOMAB phantom through experimental measurements. Results Within the range of 50 keV to 2 MeV, for rays of the same energy in the same organ of the simplified phantom and BOMAB phantom, the simulated data of detection efficiency by whole-body counting showed an error within 5%, and the experimental measurements showed an error within 10%. Conclusion We developed a simplified phantom for the calibration of the whole-body counter, demonstrating the feasibility of using the simplified phantom instead of a physical body phantom for whole-body counter calibration, which can greatly facilitate whole-body counter calibration for internal radiation monitoring.
  • Original Articles
    SUN Gangtao, WANG Fang, ZHANG Jianfeng, LI Xiaoliang, ZHAI Hezheng, ZHOU Wenshan
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    Objective To determine the current status of occupational internal exposure to 131I in the thyroid of nuclear medicine workers, to explore the influencing factors for internal exposure, and to provide a basis for the radiation safety management of nuclear medicine. Methods The cluster sampling method was used to select 162 workers practicing 131I treatment in 24 hospitals in Hubei Province, China. Thyroid 131I activity levels were measured in vitro using a portable γ-spectrometer, and the committed effective dose was estimated. Results The thyroid 131I activity detected in 13 (54.17%) hospitals was above the lower limit of detection of the instrument. Two hospitals had the highest detection rates, 62.50% and 61.90%; the difference was significant compared with the remaining 11 hospitals (P < 0.0001). Thyroid 131I was detected in 34 workers in total, with a detection rate of 20.99% and a mean activity of 179.09 ± 138.71 (6.02-589.74) Bq. The highest detection rates were found in cleaners and nurses, which were 35.71% and 33.33%, respectively, with no significant difference in detection rate between positions (least P > 0.08). The mean value of the committed effective dose was 0.68 ± 0.52 (0.02-2.22) mSv/a in the 34 workers. Conclusion The 131I consumption and workplace ventilation may be important factors affecting the level of internal exposure. It is important to strengthen the training of nuclear medicine workers on radioprotection and workflow management, as well as the regular monitoring of occupational internal exposure for 131I treatment-related workers.
  • Original Articles
    WU Mengmeng, WANG Wei, LI Xiaodun, CHEN Ling
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    Objective To assess the retention of 241Am in the whole-body bone of worker by measuring the retention of 241Am in the skull. Methods A whole-body counter with high-purity germanium detector was used to measure the 59.5 keV full-energy peak count of 241Am in the skull. The efficiency of the measurement was calibrated by the digital skull phantom combined with the geometric model of the detector. The retention of 241Am in the worker’s skull was calculated. Results The proportion of skull dry weight relative to the whole-body bone dry weight was used as the coefficient to calculate the 241Am deposition in the whole-body bone from the measured activity of skull 241Am. Conclusion With the retention of 241Am in the skull and the proportion of skull dry weight, the retention of 241Am in the whole-body bone of the worker was calculated to be about 806 Bq.
  • Original Articles
    WU Pangpang, XU Huihui, SHI Xiangwei
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    Objective To analyze the administrative penalties for radiation diagnosis and treatment in Xuzhou, China, 2018—2021, investigate the key illegal behaviors in radiation diagnosis and treatment, and provide a basis for effective supervision with targeted measures. Methods A total of 142 cases of administrative penalties were analyzed for the year of the case, the undertaker, the basic information of the subjects, the amount of penalty, and the specific illegal facts. Results From 2018 to 2021, the case number of administrative penalties for radiation diagnosis and treatment in Xuzhou was relatively stable. The cases were mainly undertaken by the municipal health supervision institution, while the number of cases handled by basic-level health supervision institutions was increasing. The administrative penalties were mainly imposed on persons and primary or non-classified medical institutions. Common illegal behaviors included occupational health management of radiation workers and personal protection during medical exposure. Conclusion We should focus on strengthening the publicity and supervision of personal protection in occupational health management and medical exposure, continue to improve the law enforcement ability of basic-level radiation health supervisors, develop a standardized management system for radiation diagnosis and treatment, innovate the supervision mode and radiation hazard notification mode, promote the “Internet + ” informatization supervision, and recommend to improve and revise radiation-related laws and regulations.
  • Original Articles
    CHEN Biao, CHEN Chunhui
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    In 2003, the responsibility of radiation source safety supervision was redivided and transferred from the health department to the environmental protection department. After the promulgation and implementation of the Rule on the Administration of Radiodiagnosis and Radiotherapy in 2006, due to the incorporation of a large number of medical practice supervision rules, the radiation health supervision of medical institutions has evolved into the radiodiagnosis and radiotherapy supervision. In the past 16 years, radiation, occupational health supervision, and medical practice supervision have not been well integrated, and there are many legal problems in radiodiagnosis and radiotherapy supervision. The regulation rules of environmental protection, metrology, and other relevant departments on radiation sources and radiation devices have been constantly changing, resulting in overly complex regulatory requirements on radiodiagnosis and radiotherapy, which increases the burden of medical institutions. This paper reviews the historical evolution and legal system changes of radiodiagnosis and radiotherapy supervision, analyzes the problems and challenges faced by the relevant regulatory departments, and proposes ways to improve the supervision system.
  • Original Articles
    CAO Qinjian, TAN Jun, REN Yue, XIONG Wanchun, WEI Xiaofeng, CHENG Wei
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    Objective Based on the measurement of the ambient dose equivalent rate of points around the novel self-shielding Zap-X radiotherapy system, its self-shielding effect was evaluated and analyzed, and suggestions were proposed for the revision and improvement of related standards in China. Methods The ambient dose equivalent rates were measured at 15 points around the Zap-X system under 6 system operating conditions. The radiation shielding effect of the Zap-X system was evaluated according to the domestic and international radiation protection standards of radiotherapy equipment. Results Measurement of ambient dose equivalent rate and dose evaluation showed that the shielding effect of the Zap-X system met the requirements of international standards, but the dose rates at some points failed to satisfy the reference control levels in the domestic standards. Conclusion Without the shielded treatment room, the self-shielding effect of the Zap-X radiotherapy system is insufficient to meet the requirements of domestic standards for radiation safety and protection. The system should be operated in the treatment room to meet domestic standards.
  • Original Articles
    ZHANG Yin, SONG Bin, XU Zhe
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    Objective To comprehensively analyze and understand the status of medical resources of radiological diagnosis and treatment in Suzhou, China, and to provide a basis for the health administration departments to reasonably plan and allocate medical radiation resources. Methods The radiological diagnosis and treatment institutions were registered on the radiation health information platform of Jiangsu province, and information was entered as required. Results There were totally 793 radiological diagnosis and treatment institutions at all levels in Suzhou, including 22 (6.04%) tertiary institutions. There were 2208 radiological diagnosis and treatment equipment. The number of X-ray diagnosis and treatment equipment per million people in Suzhou was 205.40. However, there was no class A large-scale medical equipment. Conclusion Compared with 2005, the numbers of radiological diagnosis and treatment institutions and equipment in Suzhou increased significantly. However, government departments at all levels should strengthen overall regulation and control to improve the rational allocation of high-tech medical resources.
  • Original Articles
    ZHANG Youzhong, ZHAO Yongfeng, MA Ya, HOU Dianjun, MAO Xuesong, FANG Lianying
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    Objective To investigate the occupational health status of radiation workers in Dezhou, China, explore the effects of low-dose ionizing radiation on the health of radiation workers, and provide a basis for improving the health of radiation workers. Methods A total of 1101 radiation workers in Dezhou who underwent occupational health examination in 2021 were selected. The effects of physical examination type, type of work, sex, length of service, and age on the health status of radiation workers were compared and analyzed. Results The abnormal rates of abdominal color Doppler ultrasound and eye lens were significantly higher in pre-post radiation workers than in radiation works (P < 0.05). The abnormal rates of eye lens increased with the length of service in radiation workers (P < 0.05). The abnormal rate of abdominal color Doppler ultrasound in male workers was higher than that in female workers, while the abnormal rates of blood routine and thyroid function were higher in female workers than in male workers (P < 0.05). Conclusion The abdominal rates of color Doppler ultrasound and eye lens are relatively high among radiation workers in Dezhou. It is necessary to improve the protection awareness and strengthen the level of radiation protection, so as to ensure the occupational health of radiation workers.
  • Original Articles
    SUN Peng, XU Huiping, HUANG Juan, YAN Yuan, FU Yaping
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    Objective To study and estimate the public dose constraint and the atmospheric radiation capacity of an isotope industrial park, and to provide a basis for management of radioactive effluent discharge in isotope industrial parks. Methods We collected the natural environment data, meteorological data, and population distribution and dietary data as well as the source terms of radioactive airborne effluents of an isotope industrial park. The public dose constraint value of the isotope industrial park was determined based on the natural environmental radiation hazard level. The atmospheric environmental radiation capacity of the industrial park was estimated by the all-pathways method. Results The public dose constraint value of the industrial park was 0.2 mSv/a. At the end of industrial park planning, the maximum individual effective dose to the public caused by airborne effluent discharge was 1.07×10−6 Sv/a, which accounted for 0.54% of the public dose constraint value. The proportions of discharges of airborne radionuclides to respective environmental radiation capacities ranged from 0.04% to 4.34%. Conclusion The determined public dose constraint value of the isotope industrial park can be used as the total radiation capacity of the regional atmospheric environment to constrain the discharge of radioactive effluents. The environmental radiation capacity of each radionuclide can be estimated by the all-pathways method considering the comprehensive impact of radionuclide discharges, which is suitable for the control and management of isotope production enterprises in industrial parks.
  • Original Articles
    TU Xingming, WEN Fuping, WANG Shaolin
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    Objective To establish a radioactive waste sorting process. Methods According to the current laws, regulations, standards, waste minimization requirements, and domestic good practices, the non-radioactive waste and radioactive waste were distinguished, and the radioactive waste was further sorted according to the different subsequent disposal methods of radioactive waste. The precautions for each step of the sorting process were described in detail. Results This process has been used in sorting decommissioned radioactive waste in an urban waste repository and achieved good results. Approximately 83 tons of radioactive waste and 1173 waste radioactive sources were sorted. Conclusion Good radioactive waste sorting technology can not only distinguish between radioactive and non-radioactive waste, but also facilitate the subsequent disposal of radioactive waste, which minimizes radioactive waste and protects staff and the environment.
  • Original Articles
    LU Zheng, WEN Fuping, LI Yuqin, WANG Lijiao, XIAO Wenhui, HE Lihua, XIA Yihua
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    Objective To develop a reasonable plan of monitoring personal internal exposure dose. Methods This paper introduced the methods of monitoring the individual dose and direct measurement of three representative radionuclides. Results The maximum monitoring periods were determined according to the radionuclide retention characteristics and the reporting standards and requirements, which were m(1)/m(T/2) ≤ 3 and m(T/2)/m(T) ≤ 3. The lower detection limit of the instrument was derived from the monitoring periods and the annual radionuclide intake limit, which should be lower than the derived method detection limit of the corresponding radionuclide. Then the measuring duration of the instrument that meets the corresponding conditions was derived from the derived method detection limit of the instrument and the maximum monitoring period. Conclusion Our results provide a reference for the formulation of a plan of monitoring personal internal exposure dose.
  • Original Articles
    XU Hui, ZHAO Xipeng, FENG Zechen, YUE Baorong, LIU Guoqing
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    Objective To evaluate the radiation protection of “four-in-one” dental X-ray equipment and to investigate the safety interlock of the equipment by measuring the scattered radiation at the position of the patient during operation. Methods A cone-beam CT dental phantom was used to simulate the patient’s head. The intra-oral and extra-oral components of the “four-in-one” X-ray equipment were installed in a 5 m2 room. The scattered radiation at patient position was measured using a γ/X-ray survey meter, and the effects of intra-oral and extra-oral components were compared. Results For a 5 m2 room, when CBCT was exposed under typical conditions, the dose at the patient's position was 10.70 uSv/h when there was an intra-oral component and 10.60 uSv/h when there was no intraoral component. The intra-oral part did not affect the radiation dose at the patient's position. When the intra-oral component was exposed, the dose rate at the patient's position was 4.05-6.85 uSv/h, and the extra-oral part did not affect the scattered dose of the patient examined with intra-oral components.Conclusion The evaluation of radiation protection of new equipment must comprehensively consider radiation safety and equipment operation safety. The results of this study provide suggestions for clinical radiation protection supervision and evaluation of “four-in-one” dental X-ray equipment.
  • Original Articles
    LI Peng, ZHANG Yuanyuan, ZHANG Yu, LIANG Zhiling, NIU Qingguo, XU Hui, ZHOU Jing, SHI Zhenxiang, CHEN Yan
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    Objective To investigate radiation doses to examinees undergoing computed tomography (CT) scanning of different body parts (the head, chest, and abdomen) in medical institutions of Shijiazhuang, China, and to provide a reference for optimizing radiation protection for examinees in medical institutions. Methods March 2021 to March 2022, eleven medical institutions of radiation monitoring in Shijiazhuang were surveyed for the basic information, scanning parameters, and dosimetric data of a total of 930 adults and children who received CT examinations. The dosimetric data of the subjects were analyzed and compared with the domestic and international diagnostic reference levels and the results of other cities in China. Results In the above hospitals, the CTDIvol(P50) of CT subjects in children's group were 17.42-50.45 mGy, 2.13-14.01 mGy and 3.58-28.20 mGy, respectively. DLP(P50) ranges from 228.87 to 966.97 mGy·cm, 33.20 to 296.03 mGy·cm, and 74.90 to 926.53 mGy·cm, respectively. In the adult group, the CTDIvol(P50) in the head, chest and abdomen of CT subjects were 37.28-54.05 mGy, 6.43-14.99 mGy and 8.28-18.75 mGy, respectively. DLP(P50) ranges from 372.81 to 630.56 mGy·cm, from 219.77 to 467.93 mGy·cm, and from 313.86 to 689.87 mGy·cm, respectively. The distribution of radiation doses in different-grade hospitals varied greatly. The abdomen dose of the children's hospital was higher than other hospitals. Especially the primary hospitals were significantly higher than the recommended diagnostic reference level (DRL).Conclusion In some secondary and primary hospitals, the setting of CT scanning parameters was simplified, not specific to the subjects’ age and body types. They should strictly comply with the principal of optimizing radiation protection to strengthen radiation dose optimization and supervision, reducing the radiation dose of examinees in future examinations .
  • Original Articles
    CUI Shiyue, SU Yinping, ZHAO Fengling, XING Zhiwei, LIANG Li, YAN Juan, ZHANG Yuanyuan, WANG Bo, LIU Jianxiang, HOU Changsong, CHEN Erdong, DENG Jun, SUN Quanfu
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    Since the implementation of the Measures for the Management of Radiation Workers’ Occupational Health in November 2007, it has played an extremely important role in protecting the occupational health of radiation workers. There are more than 700 000 radiation workers in about 100 000 workplaces with potential radiation exposure, as well as a large number of miners exposed to high levels of radon. As the radiation health monitoring project suggests, measures of occupational health management such as personal dose monitoring and occupational health examination of radiation workers have been widely implemented and achieved good results in the protection of radiation workers. However, the risks of chromosomal aberration and specific turbidity of the eye lens of radiation workers have increased in high-risk positions such as interventional radiology, nuclear medicine, and industrial flaw detection. The control of high radon exposure in miners needs to be strengthened. It is necessary to adapt to the new situation in view of new challenges and actively promote the revision of the Measures for the Management of Radiation Workers’ Occupational Health, so as to further improve the occupational health management of radiation workers in China.
  • Original Articles
    XI Cong, FAN Yaohua, WANG Hongtao, WANG Ziwei
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    The implementation of distance education in radiological health continuing education and training was analyzed to provide a reference for improving the quality of radiological health continuing education. The significance, measures, and advantages revealed that the application of distance education in radiological health continuing education and training was conductive to improving the quality of training and fulfilled the needs of radiological health technicians for high-quality training resources. In the future, we will continue to implement and improve distance education, promoting the high-quality development of radiological health continuing education and training.
  • Original Articles
    YU Pei, LEI Cuiping, LI Xiaoliang, SUN Quanfu
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    The purpose of establishing nuclear power plants is to meet the growing energy demand. Unfortunately, there have been five major nuclear accidents in history, which have diverse and lasting effects on individuals and society. The well-known health effects are tissue reactions caused by high radiation doses and carcinogenic effects of low radiation doses. In recent years, studies on adult residents, mothers with young children, and clean-up/decontamination workers exposed to high doses of radiation in the areas affected by nuclear power plant accidents show long-term impacts on the mental health of these people. This paper reviews these psychological impacts.
  • Original Articles
    ZHANG Feng, ZHA Daojun, BAO Yu
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    Objective To explore the value of generalized equivalent uniform dose (gEUD) optimization in radiotherapy for chest malignant tumors. Methods Sixty patients with chest malignant tumors who were treated in Center for Tumor Radiotherapy, Chizhou Municipal People’s Hospital, Anhui Province, China from October 2021 to June 2022 were enrolled; each patient underwent tumor localization with a conventional fixed computed tomography scan. The patients were divided into two groups using the same field direction and weight in the Varian Eclipse 15.6 planning system. The first group was planned using the conventional physical dose-volume objective function plus the Upper gEUD objective function, with organs at risks (OARs) optimized with the EUD values suggested by the Varian Eclipse 15.6 planning system. The second group only adopted the conventional physical dose-volume objective function for OARs optimization. The two groups were compared for the radiation doses delivered to the OARs. Results Compared with the conventional physical dose-volume objective function alone, the addition of Upper gEUD objective function resulted in no significant difference in lung V5Gy, but resulted in significant reductions in V20Gy and mean dose in the lungs; some reductions in V30Gy, V40Gy, and mean dose in the heart; and significant reductions in the maximum dose in the spinal cord. Conclusion The gEUD objective optimization can effectively protect the normal tissue in the radiotherapy for chest malignant tumors and thus is recommended in radiotherapy planning.
  • Original Articles
    LIAO Yun, WEI Lin, LU Zhongwu, LU Yongliang, TANG Yunjun
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    Objective To evaluate the value of dual-source CT angiography for evaluating the degree of coronary stenosis. Methods A total of 110 patients with a high likelihood of coronary stenosis identified by dual-source CT angiography or conventional coronary angiography were enrolled. The sensitivity, specificity, positive predictive value, negative predictive value and accuracy of dual-source CT angiography for diagnosis of coronary stenosis were evaluated with conventional coronary angiography as a gold standard. The agreement between dual-source CT angiography and conventional coronary angiography for evaluation of coronary stenosis was evaluated using Kappa statistic. Results A total of 1 401 coronary artery segments from 110 patients were displayed on conventional coronary angiography, while 1 382 segments were successfully visualized in dual-source CT angiography (98.64%). The sensitivity, specificity, positive predictive value and negative predictive value of dual-source CT angiography were 97.9%, 97.3%, 90.4% and 99.4% for diagnosis of coronary stenosis, and there was high consistence between dual-source CT angiography and conventional coronary angiography for grading coronary stenosis (Kappa statistic = 0.87, U = 58.36, P < 0.01). In addition, the sensitivity, specificity, positive predictive value, negative predictive value and accuracy of dual-source CT angiography were 94.7%, 96.8%, 83.7%, 99.0% and 96.5% for grading stenosis of coronary artery segments. Conclusion Dual-source CT angiography is accurate and reliable for diagnosis of coronary stenosis, which may be a non-invasive tool for assessment of coronary stenosis.
  • Original Articles
    YAN Huiwen, XU Hui
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    Objective To investigate the awareness of and attitudes towards radiation safety and protective measures among clinical nurses in liver interventional department, so as to provide insights into the formulation of radiation-protective measures among clinical healthcare workers. Methods A cross-sectional study was performed. Clinical nurses in liver interventional departments of class A tertiary hospitals in Jiangsu Province were sampled, and the awareness of and attitudes towards radiation safety and protective measures were investigated using self-designed questionnaires. Results A total of 112 questionnaires were allocated, and 97 valid questionnaires were recovered, with an effective recovery rate of 86.61%. The awareness of questions including “interventional therapy may cause radiation exposure” and “wearing lead apron may reduce radiation exposure” was both 100.00% among respondents, and the awareness of questions including “radiation exposure may cause congenital malformations in babies”, “radiation exposure may cause cancers such as skin cancer and leukemia”, “radiation exposure may cause death”, “wearing lead goggles may reduce radiation exposure”, and “wearing thyroid shields may reduce radiation exposure” was all higher than 95.00%, while the awareness of questions “radiation exposure may cause cataract of the eye lens” and “radiation exposure may cause bone marrow depression” was relatively low. Respondents presented high-level attitudes towards lead aprons, and low-level attitudes towards goggles and thyroid shields. Conclusion The awareness of radiation safety knowledge is high among clinical nurses in liver interventional departments; however, an overall low-level attitude is seen towards radiation-protective measures. Health education pertaining to radiation safety and protective measures is required to be improved, so as to increase the compliance to radiation-protective measures.