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  • Original Articles
    E2E testing of Cyberknife lung tracking using a homemade lung phantom
    WEI Xiao, MA Xiangjie, LI Mingsheng, ZHANG Zhengzhao, LIU Ya, YANG Yuze, CHENG Jinsheng
    2024, 33(1): 1-6. https://doi.org/10.13491/j.issn.1004-714X.2024.01.001
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    Objective To verify the feasibility of using a homemade lung phantom for quality control of Cyberknife by comparing the measurement results of the homemade lung phantom and CIRS dynamic phantom in E2E testing of Cyberknife lung tracking. Methods The patient treatment process was simulated, including CT positioning, plan design, irradiation implementation, film scanning, and analysis using the homemade phantom and CIRS phantom. The two phantoms were measured five times using MLC under the S7 generation Cyberknife and five times using Iris under the M6 generation Cyberknife. The differences in measurement results between the two phantoms were analyzed using independent sample t-test. Results For the S7 generation Cyberknife, the statistical analysis of differences between the two phantoms in the detection values on the X-axis, Y-axis, Z-axis, and total deviation showed P values of 0.236, 0.175, 0.289, and 0.668, respectively. For the M6 generation Cyberknife, the statistical analysis showed P values of 0.880, 0.891, 0.573, and 0.433, respectively. The P values were all > 0.05. Therefore, there were no statistically significant differences in the detection results between the homemade lung phantom and the CIRS phantom under the S7 and M6 generation Cyberknife. The total deviation values were <1.5 mm. Conclusion The homemade lung phantom and CIRS phantom have consistent measurement results in the E2E testing of Cyberknife lung tracking and meet the requirements of Report of AAPM TG-135 and WS 667-2019 standard. Therefore, the homemade lung phantom is feasible for clinical quality control of Cyberknife.
  • Original Articles
    Calculation of retention fractions in main source organs following acute americium inhalation based on ICRP biokinetic models
    CHEN Qianlan, LUO Zhiping, LIU Senlin
    2024, 33(1): 7-12. https://doi.org/10.13491/j.issn.1004-714X.2024.01.002
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    Objective To provide a reference for avoiding the harm to critical target organs following considerable inhalation exposure to the transuranium element americium (Am) as well as post-accident decorporation or other radiation protection measures. Methods We established calculation programs based on the generic criteria for internal radiation emergency preparedness and response in the IAEA Safety Guide No.GSG-2 and current new ICRP biokinetic models and parameters, taking an inhalation of 241Am (activity mean aerodynamic diameter of 5 μm, σ = 2.5) by an adult worker as an example; and determined that the critical target organs were the lung AI region, red bone marrow, and the main source organs leading to acute doses to the critical target organs were the lung AI region, blood, and trabecular bone surface. Results The retention fractions in the main source organs over time after 241Am inhalation were calculated. Conclusion After being absorbed into blood, Am moves quickly to other parts, and Am of different absorption types shows similar early changes in retention fractions in blood: the retention fractions of Am of S, M, and F types in blood peak around 0.03 d, and then halve around 1.7 d. Inhaled Am shows different changes over time in retention fractions in the lung AI region and trabecular bone surface in the early stage: the retention fractions of S- and M-type Am in the lung AI region change little with time, while F-type Am transfers quickly from the lung to blood; In trabecular bone surface, S-type Am increases quickly in the first 7 d, M-type Am gradually increases mainly in the first 2 weeks, and F-type Am increases quickly in the first 2 d.
  • Original Articles
    Effects of fractionated low-dose ionizing radiation in the induction of EA.hy926 cell senescence
    CAI Yashi, HUANG Weixu, ZHANG Lingyu, ZHANG Min, LI Huixian, WEN Changyong, HE Zhini, ZOU Jianming, CHEN Huifeng
    2024, 33(1): 13-20. https://doi.org/10.13491/j.issn.1004-714X.2024.01.003
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    Objective To investigate the mechanism of fractionated low-dose ionizing radiation (LDIR) in the induction of EA.hy926 cell senescence. Methods EA.hy926 cells were irradiated with X-ray at 0, 50, 100, and 200 mGy×4, respectively, and cultured for 24, 48, and 72 h. Several indicators were measured, including the levels of cellular senescence-associated β-galactosidase (SA-β-gal) staining, mRNA levels of senescence-associated cell cycle protein-dependent kinase inhibitor genes CDKN1A and CDKN2A, reactive oxygen species (ROS), total antioxidant capacity (T-AOC), and phosphorylated H2A histone family member X (γ-H2AX). Results After 4 fractionated LDIR, compared with the control group, the treatment groups showed increased nucleus area, blurred cell edge, and increased SA-β-gal positive area (P < 0.05) at 24, 48 and 72 h. After 4 fractionated LDIR, the mRNA level of CDKN1A increased in the 100 and 200 mGy×4 groups at 24 and 48 h (P < 0.05), and CDKN2A mRNA level increased in the 100 and 200 mGy×4 groups at 48 and 72 h (P < 0.05). The fluorescence intensity of ROS increased in treatment groups at 24, 48, and 72 h after 4 fractionated LDIR (P < 0.05). After 4 fractionated LDIR, the T-AOC level increased in the 100 and 200 mGy×4 groups at 24 h (P < 0.05), and T-AOC level increased in all treatment groups at 48 and 72 h (P < 0.05). After 4 fractionated LDIR, γ-H2AX fluorescence intensity increased in all treatment groups at 24 h (P < 0.05), and the fluorescence intensity increased in the 100 and 200 mGy×4 groups at 48 and 72 h (P < 0.05). Conclusion Fractionated LDIR can induce cellular senescence in EA.hy926 cells by impacting the cellular oxidation-antioxidation and oxidative damage levels, and the effects were relatively evident at 100 and 200 mGy.
  • Original Articles
    BMSCs promote M2 macrophage polarization to attenuate acute radiation-induced lung injury
    ZHANG Xinhui, NIU Shiying, YAO Shutong, ZHANG Xiaoyue, CAO Xuetao, GAO Xue, ZHAO Guoli, CHEN Jingkun, ZHANG Yueying
    2024, 33(1): 21-27. https://doi.org/10.13491/j.issn.1004-714X.2024.01.004
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    Objective To investigate the therapeutic effects of bone marrow mesenchymal stem cells (BMSCs) for radiation-induced lung injury (RILI) and the underlying mechanism. Methods Forty-five healthy adult male C57BL/6 mice were randomly divided into control, model, and BMSCs groups. The model and BMSCs groups received a single irradiation dose of 20 Gy to the chest, while the control group did not receive X-ray irradiation. For the BMSCs group, an injection of 1×106 BMSCs cells was administered via the tail vein within 6 h after irradiation. In the 5th week, the lung tissue was taken to observe pathological changes with HE staining; examine the expression of the inflammatory factors interleukin-6 (IL-6) and tumor necrosis factor-α (TNF-α) with immunohistochemical staining; observe the polarization of macrophages with immunofluorescence staining; and measure the expression of the epithelial-mesenchymal transition markers E-cadherin, N-cadherin, and vimentin proteins by Western blot. Results After radiation, the model group developed pulmonary vasodilation and congestion with septal thickening and inflammatory cell infiltration, and these changes were markedly reduced in the BMSCs group. The model group showed significantly down-regulated expression of IL-6 and TNF-α compared with significantly increased levels in the model group (P < 0.01, P < 0.05). Treatment with BMSCs significantly increased the polarization of lung macrophages towards the M2 type, while significantly decreasing the abnormally increased N-cadherin and vimentin levels in RILI mice (P < 0.05, P < 0.01). Conclusion BMSCs have therapeutic effects for RILI mice, which may be through promoting macrophage polarization from M1 to M2.
  • Original Articles
    Effects of occupational radiation exposure on peripheral blood lymphocyte count and cell cycle in logging workers
    LI Weiguo, GAO Gang, PAN Yan, LI Hailiang, RUAN Jianlei, PIAO Chunnan, FU Jinghong, LIU Jianxiang
    2024, 33(1): 28-32,39. https://doi.org/10.13491/j.issn.1004-714X.2024.01.005
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    Objective To investigate the effects of prolonged low-dose neutron-γ radiation on peripheral blood lymphocytes of logging workers. Methods The health information of workers in a logging company was collected by on-site blood sample collection and questionnaire survey. Individual doses of γ and neutron radiation were recorded using LiF elements and CR-39, respectively. Lymphocyte count in peripheral blood was measured by blood cytometer. Cell cycle and cyclins were detected by flow cytometry. Results The annual dose of some logging workers exceeded 5 mSv. Lymphocyte counts showed a difference of 15% between the group exposed to the lowest annual dose of 0–1 mSv (mean: 2.45×109/L) and the group exposed to the highest annual dose of 5–25 mSv (mean: 2.08×109/L). In comparison to pre-shift workers, logging workers exhibited a G1-phase arrest in the lymphocyte cycle, along with increased expression of cyclins p21 and CDK2. Conclusion Prolonged exposure to low-dose neutron-γ radiation leads to reduced lymphocyte counts as well as changes in lymphocyte cycle and cyclin expression.
  • Original Articles
    Hydrogen therapy promotes macrophage polarization to the M2 subtype by inhibiting the NF-κB signaling pathway
    GAO Xue, NIU Shiying, SONG Guohua, LI Lulu, ZHANG Xiaoyue, PAN Wentao, CAO Xuetao, ZHANG Xinhui, SUN Meili, ZHAO Guoli, ZHANG Yueying
    2024, 33(1): 33-39. https://doi.org/10.13491/j.issn.1004-714X.2024.01.006
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    Objective To investigate the role of hydrogen therapy in reducing radiation-induced lung injury and the specific mechanism. Methods Forty C57BL/6 mice were randomly divided into four groups: normal control group, model group, hydrogen therapy group I, and hydrogen therapy group II. A mouse model of radiation-induced lung injury was established. The pathological changes in the lung tissue of the mice were examined with HE staining. Immunofluorescence staining was used to detect the expression of surface markers of M1 and M2 macrophages to observe macrophage polarization. The expression of interleukin (IL)-6, tumor necrosis factor-α (TNF-α), and IL-10 in the lung tissue was measured by immunohistochemistry. The expression of nuclear factor-kappa B (NF-κB) p65 and phosphorylated NF-κB (P-NF-κB) p65 was measured by Western blot. Results HE staining showed that compared with the control group, the model group exhibited alveolar septal swelling and thickening, vascular dilatation and congestion, and inflammatory cell infiltration in the lung tissue; the hydrogen groups had significantly reduced pathological damage and inflammatory response than the model group, with more improvements in hydrogen group II than in hydrogen group I. Immunohistochemical results showed that compared with those in the control group, the levels of the inflammatory cytokines IL-6 and TNF-α were significantly increased in the model group; the hydrogen groups showed significantly decreased IL-6 and TNF-α levels and a significantly increased level of the anti-inflammatory factor IL-10 than the model group, which were more marked in hydrogen group II than in hydrogen group I. Immunofluorescence results showed that compared with the control group, the expression of the surface marker of M1 macrophages in the model group was significantly upregulated; the hydrogen groups showed significantly downregulated M1 marker and significantly upregulated M2 marker, and hydrogen group II showed significantly increased M2 marker compared with hydrogen group I. Western blot results showed that compared with that in the control group, the ratio of P-NF-κB p65/NF-κB p65 in the model group was significantly increased; the P-NF-κB p65/NF-κB p65 ratio was significantly reduced in the hydrogen groups than in the model group, and was significantly lower in hydrogen group II than in hydrogen group I. Conclusion Hydrogen inhalation therapy may reduce the inflammatory response of radiation-induced lung injury by inhibiting the NF-κB signaling pathway to promote the polarization of the macrophage M1 subtype to the M2 subtype.
  • Original Articles
    Analysis of the results of the nationwide interlaboratory comparison of gross α and gross β radioactivity measurement
    CHEN Yongyong, SHI Yanghai, SHI Yuhua, WANG Ping, LU Yuansheng
    2024, 33(1): 40-45. https://doi.org/10.13491/j.issn.1004-714X.2024.01.007
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    Objective To summarize and improve the related technical issues by analyzing the nationwide interlaboratory comparison of gross α and gross β radioactivity measurement over the years. Methods According to the requirements of interlaboratory comparison and the national standards, the gross α and gross β radioactivity in water were measured, and the results were analyzed to identify the influencing factors. Results From 2018 to 2022, our laboratory participated in five nationwide interlaboratory comparisons of gross α and gross β radioactivity measurement. The Z-test values for gross α and gross β measurement ranged from -0.24 to 1.8 and -1.4 to 0.35, respectively. The relative deviations ranged from -4% to 32% and -18% to 6%, respectively. All comparisons were within the acceptable ranges. Conclusion The analysis of comparisons showed that the results were within the acceptable ranges. The relative deviations between the measurement and the reference values have decreased over the years. The summary and improvement of related technologies have improved the measurement accuracy.
  • Original Articles
    Discussion on results of national measurement capability comparison assessment for gross α and gross β radioactivity in water and calculation formulas for spike recovery
    LI Wenrui, YI Jiaqin, LI Kui
    2024, 33(1): 46-50,55. https://doi.org/10.13491/j.issn.1004-714X.2024.01.008
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    Objective To summarize and analyze the difficulties and key points in the measurement of gross α and gross β radioactivity in water based on the results of national measurement capability comparison assessment, and provide the basis and reference for the future work and the development of new local standards. Methods The research team participated in the comparison assessment for measurement of the gross radioactivity in water samples organized by National Institute for Radiological Protection, Chinese Center for Disease Control and Prevention. According to the comparison assessment results and the content in the national standard GB/T 5750.13—2023 (published draft), the steps of spike recovery involved during the measurement were analyzed and discussed. Two different formulas used for spike recovery calculation were analyzed for their impact on the final measurement results. Results When the spike recovery F(derived) derived from the formulas was used for result calculation, the spike recovery ranged as follows: gross α: 63.00%-84.60%, and gross β: 95.0%-99.1%; 3/6 of the comparison results were determined as excellent and 3/6 as pass as a whole (among them, 4 were excellent and 2 were pass for both single gross α assessment items and single gross β assessment items). When the spike recovery F from the GB/T 5750.13—2023 (published draft) was used for result calculation, the spike recovery ranged as follows: gross α: 39.69%-71.57%, and gross β: 90.25%-98.21%; 5/6 of the comparison results were determined as fail and 1/6 as pass (among them, 5 were fail and 1 was pass for single gross α assessment items; 5 were excellent and 1 was pass for single gross β assessment items). When two different formulas were used for spike recovery calculation, there was a significant difference in gross α radioactivity measurement (t = 4.27, P = 0.03 < 0.05), but there was no significant difference in gross β radioactivity measurement (t = 0.667, P = 0.524 > 0.05). Conclusion In the measurement of gross α and gross β radioactivity in water, appropriate reference to the spike recovery has a great influence on the measurement results. Therefore, quality control should be strengthened to further ensure the accuracy of measurement.
  • Original Articles
    Analysis of uranium concentration in surface water and drinking water in Beijing, China
    WANG Huan, SUN Yaru, YAO Meinan, BAI Bin, MENG Qinghua, MA Yongzhong
    2024, 33(1): 51-55. https://doi.org/10.13491/j.issn.1004-714X.2024.01.009
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    Objective To explore the uranium concentration in surface water and drinking water in Beijing, China and the relationship between uranium concentration and gross α activity concentration. Methods Water samples were collected from 16 districts in Beijing. Uranium concentration and gross α activity concentration were measured with WGJ-III trace uranium analyzer and LB6008 six-channel α/β counter using the ultraviolet fluorescence and thick source methods. Results The uranium concentrations in surface water and drinking water were 1.131 and 1.572 μg/L, respectively. The gross α activity concentrations in surface water and drinking water were 0.059 and 0.074 Bq/L, respectively. There were no significant differences in uranium concentration and gross α activity concentration between surface water and drinking water (P > 0.05). The uranium concentration was positively correlated with the gross α activity concentration, with a correlation coefficient of 0.700 (P < 0.05). The gross α activity concentration was determined by the uranium concentration with a determination coefficient of 48%. The committed effective dose of 238U in drinking water was between 3.284×10-5 and 1.640×10-3 mSv, with an average value of 5.400×10-4 mSv. Conclusion The uranium concentration and gross α activity in the surface water and drinking water in Beijing fluctuate and remain in the background range. These values are much lower than the recommended limits of 0.03 mg/L and 0.5 Bq/L stipulated in the GB 5749-2021 Standard for Drinking Water Quality. The annual committed effective dose of 238U through drinking water ingestion is very small.
  • Original Articles
    Development of an online radioactive xenon gas monitoring system for nuclear facilities
    GUO Luzhen, PANG Hongchao, WANG Chuangao, ZHANG Yanbiao, WANG Ying, WU Mengmeng, DONG Xinfang, CHEN Ling
    2024, 33(1): 56-60. https://doi.org/10.13491/j.issn.1004-714X.2024.01.010
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    Objective Nowadays, radioactive xenon isotopes, including 131mXe, 133mXe, 133Xe, and 135Xe, are primarily released into the atmosphere through various reactor operation and major accidents of reactors. To improve the online monitoring capability of xenon in nuclear facilities and their gaseous effluents, a highly sensitive online xenon monitoring system was developed to monitor, warn, and alarm the activity concentration of radioactive xenon. Methods The online monitoring system for radioactive xenon gas in nuclear facilities was established using xenon membrane separation and concentration, xenon high-efficiency selective adsorption, and low-background gamma-ray spectrometry analysis methods. Results Under the operation mode of one-hour sampling and one-hour measuring, the minimum detectable activity concentration of the radioactive xenon online monitoring system for 133Xe was approximately (1.43 ±0.03) Bq/m3. Conclusion This system can be effectively used for online monitoring of xenon activity concentration in nuclear facilities such as nuclear power plants and isotope production reactors, as well as in gaseous effluents. It helps improve the safety level of personnel, the environment, and nuclear facilities.
  • Original Articles
    An analysis of results of 392 times of CT quality control and room radiological protection testing in Guangdong Province, China
    CHENG Xiyuan, LIAO Yanpeng, LIU Shupeng, WANG Chuang, ZHOU Meijuan
    2024, 33(1): 61-67. https://doi.org/10.13491/j.issn.1004-714X.2024.01.011
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    Objective To provide a theoretical basis for radiation health supervision through an analysis of the situation of computed tomography (CT) equipment quality control and CT room radiological protection in Guangdong Province, China in recent years. Methods We collected the data of 392 times of CT quality control and radiological protection testing by a third-party radiological health technical service institution in Guangdong Province from 2019 to 2021. We analyzed the levels of CT-owning hospitals, CT manufacturers, CT quality control test results, and the pass rate of radiation protection tests. Results The examined CT scanners were from different levels of hospitals in Guangdong Province, and were manufactured by nine major CT equipment manufacturers at home and abroad. The pass rate of CT room radiological protection was 99.88%, and the ambient dose equivalent rates of five monitoring points exceeded the limit, with four at the control room door and one at the shield wall of the room. The overall pass rate of CT equipment quality control was 99.49%, and the non-conforming parameters were the accuracy of positioning light and the deviation of reconstructed slice thickness. Conclusion In recent years, CT equipment quality control and room radiation protection in Guangdong Province have been at a high level.
  • Original Articles
    Analysis of current status of radiation protection in non-medical radiation workplaces in Yantai, China, 2022
    CHI Xin, LI Li, SUN Yingchao, WANG Kelin, YAN Xige
    2024, 33(1): 68-73. https://doi.org/10.13491/j.issn.1004-714X.2024.01.012
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    Objective To investigate the current status of radiation protection in non-medical radiation workplaces in Yantai, China, and to provide a scientific basis for occupational health management in non-medical radiation workplaces. Methods Non-medical radiation workplaces in Yantai were investigated using a questionnaire survey in 2022, including radiation source term, occupational health examination, personal dose monitoring, personal protective equipment, and radiation protection testing workplaces. Data were entered by a double-entry method and then analyzed. Results There were 56 non-medical radiation workplaces in Yantai, covering manufacturing, nonferrous metal ore mining, nuclear power plant, transportation, and technical services. There were 0 Class I radiation device, 150 Class II radiation devices, and 10 Class III radiation devices; there were 80 Class I radiation sources, 16 Class II radiation sources, 14 Class III radiation sources, 62 Class IV radiation sources, and 135 Class V radiation sources. There were 998 radiation workers, with an occupational health examination rate and personal dose monitoring rate of 98.3%. Among the 56 non-medical radiation workplaces, 47 (83.9%) were equipped with radiation protection monitoring instruments, 24 (51.1%) workplaces had verified the radiation protection monitoring instruments, with 2017 personal dose monitoring instruments and 2327 personal protective equipment in place, 42 (75%) workplaces carried out occupational health assessments, 44 (78.6%) workplaces carried out self-detection, and 53 (94.6%) workplaces carried out entrusting detections (monitoring pass rate: 100% [53/53]). The declaration rate of occupational hazard items was 87.5% (49/56). Conclusion There is still a gap between the current status and the requirements in the national regulations and standards regarding radiation protection in non-medical radiation workplaces. Therefore, the supervision and management of non-medical radiation workplaces should be further strengthened, especially the configuration and verification of radiation protection monitoring instruments.
  • Original Articles
    Analysis of current radiation protection and occupational health management in non-medical institutions in Hebei Province, China, 2022
    GUO Dawei, SUN Yuan, LUO Yingnan, ZHANG Jingzhan, YANG Yanwen, ZHOU Kaijian
    2024, 33(1): 74-79. https://doi.org/10.13491/j.issn.1004-714X.2024.01.013
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    Objective To investigate the number, distribution, and types of radiation of non-medical radiation institutions in Hebei Province, China, and to explore the current radiation protection in the employing units and occupational health management of radiation workers in 2022. Methods A questionnaire survey was conducted in the non-medical institutions engaged in nuclear technology application in Hebei Province, and different types of employing units were selected to monitor the radioactivity level in the workplace. Results A total of 681 non-medical institutions engaged in radiation technology application completed the survey, covering all cities with subordinate districts in the province, including 1605 radioactive devices, 2960 active devices, 45 non-uranium metal mines, and 14 non-sealed workplaces. A total of 8617 radiation workers were surveyed, with a personal dose monitoring rate of 70.9%, a radiation protection training rate of 61.1%, and an occupational health examination rate for radiation workers of 59.3%. A total of 614 radiation protection monitoring instruments were provided, with a personal protective equipment allocation rate of 51.1% and a personal dose alarm device allocation rate of 51.8%. The radiation occupational hazardous factor testing was completed for 54 workplaces, and the results were all qualified. Conclusion There are still significant deficiencies in personal dose monitoring in the radiation work units in non-medical institutions and occupational health examination in the radiation work units in our province. The health administrative departments should strengthen health supervision and law enforcement, enhance radiation protection and skill training for employers, and more effectively control the impact of radiation hazards on personnel health.
  • Original Articles
    Development and performance test of unmanned aerial vehicle-borne CeBr3 radiation monitoring system
    FANG Jiangqi, AN Zhengwei, ZHANG Wenfeng, LIU Linfeng, YANG Jinzheng, LIU Xue, LI Jiangkun
    2024, 33(1): 80-86. https://doi.org/10.13491/j.issn.1004-714X.2024.01.014
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    Objective To develop an unmanned aerial vehicle (UAV)-borne radiation monitoring system with high detection efficiency and nuclide identification ability for airborne monitoring in nuclear emergency. Methods The UAV-borne CeBr3 radiation monitoring system was composed of four cerium bromide (CeBr3) crystal detectors coupled with silicon photomultipliers (SiPMs) and other components including integrated modules, intelligent electronic devices, and new composite materials. Results According to various performance tests on the system, the crystal energy resolution was better than 5% (@0.662 MeV), the peak drift of the energy spectrum was within ±1 channel, the linear fit of energy was 0.99997, the change in the count rate of each energy window during 12 h long-term measurement was less than 5%, and the detection efficiency was higher compared with that of NaI (Tl) detectors of the same volume. Conclusion Through ground point source testing and theoretical calculation, the system has reliable ability to identify radionuclides, which can be used in nuclide identification and the preparedness and response for nuclear and radiation emergencies.
  • Original Articles
    A practice case of monitoring waste resin clearance in a nuclear power plant
    TU Xingming, WEN Fuping, XU Xutao, HOU Shuguo, LOU Hailin, PAN Jingshun, WANG Chuangao
    2024, 33(1): 87-91. https://doi.org/10.13491/j.issn.1004-714X.2024.01.015
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    Objective To establishment a process of monitoring waste resin clearance in nuclear power plants, and to meet clearance requirements and simplify the monitoring work. Methods In accordance with the requirements specified in current laws, regulations, and standards in China, as well as the practice of slightly polluted waste resins generated during the operation of nuclear power plants, in-depth discussion was conducted on sampling methods, sample uniformity and representativeness tests, radiation monitoring contents and methods, and simplified monitoring processes, in order to accurately monitor the radionuclide activity of waste resins to be cleared. Results A process was established to monitor waste resin clearance in nuclear power plants. A total of 55 barrels of waste resins were cleared and the radiation levels met the requirements. Conclusion An effective clearance process can facilitate the sampling of representative resins, improve the accuracy of monitoring data, differentiate radioactive waste from cleared waste, and simplify the monitoring process. Our results provide a basis and reference for future waste resin clearance.
  • Original Articles
    Occupational health management of radiation workers in non-medical institutions in Shanxi Province, China
    GUO Lili, XU Jihong, ZHENG Lixian, WU Fengjiao, SHI Jianhua, ZHAO Xiaoai, ZHAO Qiyu
    2024, 33(1): 92-95. https://doi.org/10.13491/j.issn.1004-714X.2024.01.016
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    Objective To understand the basic information of the number, classification, and distribution of radiation work units in non-medical institutions in Shanxi Province, China, and to analyze the status quo of health management and radiation protection measures for radiation workers, so as to provide a scientific basis for occupational exposure protection in non-medical radiation work units and better protect the occupational health rights and interests of radiation workers. Methods A questionnaire survey was conducted to investigate some non-medical institutions in Shanxi Province. On-site testing was carried out to determine the risk factors for radioactive occupational diseases in the selected non-medical institutions. Results In 220 non-medical institutions, there were 340 radiation devices and 2284 radioactive sources. The rate of individual dose monitoring was 92.7% and the rate of occupational health examination was 87.2%. These devices were equipped with 325 detection instruments for radiation protection, 1316 personal protective equipment, and 730 personal dose alarms. Radiation occupational disease risk factors were investigated in 101 institutions. Conclusion The occupational health management of radiation workers in non-medical institutions in Shanxi Province is generally in line with the national standards. However, there is still a big gap with the level of occupational health management in medical institutions. The health administration departments should clarify the management measures for non-medical institutions and strengthen their supervision and management functions.
  • Original Articles
    Effects of ionizing radiation on blood pressure and electrocardiography among healthcare workers in department of cardiovascular diseases
    LIU Dan, HUANG Xiu, XU Hanli
    2024, 33(1): 96-100. https://doi.org/10.13491/j.issn.1004-714X.2024.01.017
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    Objective To examine the effects of ionizing radiation on blood pressure and electrocardiography among healthcare workers in department of cardiovascular diseases, and to provide a reference for formulating the protective interventions against radiation exposure. Methods A total of 127 healthcare workers with radiation exposure in the Department of Cardiovascular Diseases of The 904th Hospital of the Joint Logistics Support Force of the PLA from 2018 to 2022 were included in the observation group. Meanwhile, 127 age- and gender-matched healthcare workers without radiation exposure in the same department during the same study period were included in the control group. The systolic blood pressure, diastolic blood pressure, heart rate, and the detection rates of hypertension and abnormal electrocardiography were compared between groups. Results There were no significant differences between groups in mean age (t = 0.77, P > 0.05), sex (χ2 = 0.02, P > 0.05), prevalence of smoking (χ2 = 0.28, P > 0.05), and alcohol consumption (χ2 = 0.02, P > 0.05). There were significant differences between the observation and control groups in systolic blood pressure [(127.77 ±15.43) mmHg vs. (111.23 ±19.10) mmHg; t = 4.21, P < 0.05], diastolic blood pressure [(79.32 ±8.23) mmHg vs. (69.91 ±10.21) mmHg; t = 4.09, P < 0.05], prevalence of hypertension [17.32% (22/127) vs. 8.66% (11/127); χ2 = 4.21, P < 0.05], heart rate [(81.10 ±11.27) beats/min vs. (70.45 ±10.55) beats/min; t = 4.33, P < 0.05], and abnormal rate of electrocardiography [21.26% (27/127) vs. 10.24% (13/127); χ2 = 5.82, P < 0.05]. Conclusion Ionizing radiation affects blood pressure and electrocardiography among healthcare workers in department of cardiovascular diseases. The prevention and monitoring of radiation exposure and occupational physical examination should be improved among healthcare workers with exposure to radiation in the department of cardiovascular diseases, with aims to reduce the hazard of radiation exposure and protect the health of healthcare workers.
  • Original Articles
    Relationship between cerebrovascular reserve capacity and white matter lesions in the elderly based on magnetic resonance imaging
    LUO Lihong, GONG Wenru, LI Mei, XING Xizi, ZHANG Hua
    2024, 33(1): 101-105,110. https://doi.org/10.13491/j.issn.1004-714X.2024.01.018
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    Objective To investigate the relationship between cerebrovascular reserve (CVR) capacity and white matter lesions in elderly people. Methods We included 315 participants aged ≥ 60 years in Jinan area of Shandong Province from May 2018 to July 2019. They underwent transcranial Doppler ultrasonography for assessing CVR, breath holding index (BHI), and arterial pulsatility index (PI). According to CVR capacity, they were divided into normal CVR group (CVR ≥ 20%, n = 206) and impaired CVR group (CVR < 20%, n = 109). Magnetic resonance imaging was performed to evaluate periventricular, subcortical, and total white matter hyperintensity (WMH) volumes and Fazekas scores. Results Compared with the normal CVR group, the impaired CVR group showed significantly higher volumes of periventricular, subcortical, and total WMHs and significantly higher proportions of Fazekas scores ≥ 2 (P < 0.01). Periventricular, subcortical, and total WMH volumes were negatively correlated with CVR (r = -0.70, -0.66, -0.73, P < 0.01) and BHI (r = -0.64, -0.65, -0.68, P < 0.01) and positively correlated with PI (r = 0.60, 0.65, 0.65, P < 0.01). After adjusting for confounding factors, periventricular, subcortical, and total WMH volumes were still negatively correlated with CVR and BHI (P < 0.01) and positively correlated with PI (P < 0.01). The logistic regression analysis showed that the risks of periventricular, subcortical, and total Fazekas score ≥ 2 in the impaired CVR group were 1.96 times (95% confidence interval [CI]: 1.17-3.27, P < 0.01), 1.84 times (95% CI: 1.11-3.05, P < 0.05), and 2.33 times (95% CI: 1.30-4.18, P < 0.01) that of the normal CVR group, respectively. Conclusion Impaired CVR is an independent risk factor for white matter lesions in the elderly.
    • Review Articles
  • Review Articles
    Progress of research on the preventive and therapeutic agents against radiation-induced injuries
    XUE Junfeng, SUN Shu, JIANG Yunyun, QI Weili, HU Wei
    2024, 33(1): 106-110. https://doi.org/10.13491/j.issn.1004-714X.2024.01.019
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    Radiation-induced injury, a body dysfunction caused by irradiation, is associated with the dose, duration, and speed of radiation and is predominantly derived from radiation therapy for patients with malignant tumors. The current clinical treatment mainly includes amelioration of injury, alleviation of symptoms, and improvements in function restoration of the affected sites because of lack of targeted agents specific to radiation-induced injuries. Research and development of preventive and therapeutic agents against radiation-induced injuries are of great significance to reduce the body damages caused by radiotherapy and improve the quality of life of cancer survivors. This review summarizes the radiation-induced injury and its mechanisms, radioprotectants, and therapeutic agents for radiation, and proposes future development directions, so as to provide a reference for alleviation of radiation-induced injury and improvement in prognosis.