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Mechanism of action and efficacy of radon springs on human body and dose evaluation XIE Silei, GAO Bai, LIU Yuanyuan, MA Wenjie, LI Sisi RADIATION PROTECTION    2025, 45 (2): 119-132.   Abstract （115）      PDF（pc） （5034KB）（227）       Knowledge map    Save With the rise of the concept of “great health”, radioactive springs such as radon hot springs have become an emerging health tourism and convalescence way to meet the needs of people seeking natural, non-pharmacological therapies, which has great potential and application value. Meanwhile, radon in water is an important source of indoor radon, which is classified as one of the carcinogens by the World Health Organization, and the concentration limit and effective dose of radon have become scientific issues of concern in the field of environmental and ecotoxicological toxicology, which restricts the development of radon springs in terms of medical treatment. This paper centers on the development of radon spring bath therapy, the formation and distribution of radon springs, the non-specific and biological mechanism of radon springs on human body, the efficacy of radon springs, and the progress of radon springs dose limit. This paper focuses on the review of radon springs for the course of treatment of different types of diseases and the clinical effect. On the basis of the review, the effective dose due to the inhalation of radon and its daughters by convalescents and the results of the effect of radon on different organs or tissues are calculated; the relationship between the concentration and annual effective dose of radon and the effects on different organs or tissues are analyzed. This paper also analyzes the relationship between radon concentration and annual effective dose and residence time, so as to provide theoretical and technical support for the public to safely and scientifically utilize the benefits of radon springs. Reference | Related Articles | Metrics

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Investigation and analysis of radioactivity level in lead and zinc mines in Sichuan Province ZHU Xiaojiao RADIATION PROTECTION    2025, 45 (3): 221-228.   Abstract （98）      PDF（pc） （988KB）（48）       Knowledge map    Save In order to establish the data archive of radioactivity level of lead and zinc mines in Sichuan province, radiation level of 33 lead and zinc mines in Sichuan province was investigated, and the terrestrial gamma radiation dose rate and mineral radionuclide activity concentration (238U, 226Ra, 232Th) were studied. According to the investigation results, all the estimated dose was lower than the annual dose limit of 20 mSv for occupational personnel. The annual exposure dose of mining enterprises is the highest, and that of smelting enterprises is the lowest. The radiation dose was mainly from γ external exposure. The results show that it is necessary to strengthen the radiation safety management of lead-zinc mining enterprises and strengthen the external radiation protection of employees, which can provide data support for the control of radioactive pollution in lead-zinc mines. Reference | Related Articles | Metrics

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IAEA radiation safety standard committee and recent concerns on radiation safety issues LIU Liye, CHEN Faguo, ZHANG Jintao, TUO Fei, TAO Weiding, JIN Haijing RADIATION PROTECTION    2025, 45 (2): 101-107.   Abstract （95）      PDF（pc） （3678KB）（130）       Knowledge map    Save The IAEA Safety Standards Series with 145 safety standards and a logical top-down relationship have been largely accomplished according to the 2008 Long Term Structure. Meanwhile, a new Long term structure looking into next 10-15 years will be ready in 2026, fitting to the emerging of artificial intelligence, climate change, new types of reactor, and so on. The main work of IAEA Radiation Safety Standards Committee (RASSC) is introduced and recent concerns on radiation safety issues are discussed in this paper. A new comprehensive safety guide is being developed by RASSC to address the challenges in identification and management of existing exposure situations. Although the International Commission on Radiological Protection (ICRP) has updated the internal dose coefficients for occupational exposure, RASSC will not revise relative safety standards in the near future and will continue to collect the experience feedback of member countries. With the application of new radiotherapy technologies, RASSC has also focused on radiation protection in radionuclide therapy and the secondary malignancies of radiotherapy survivors. Reference | Related Articles | Metrics

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Preliminary analysis on the driving force for the development of radiation protection LIU Liye, WANG Renze, YU Weiyue, AN Hongxiang, SUN Qinghong, GAO Zequan RADIATION PROTECTION    2025, 45 (3): 197-206.   Abstract （86）      PDF（pc） （7697KB）（60）       Knowledge map    Save In order to explore the important driving forces for the development of radiation protection, the development history of representative international organizations, advanced countries and regions of nuclear energy and China was briefly reviewed in terms of radiation protection. Therefore, five important driving forces for the development of radiation protection were summarized, namely, the deep understanding of radiation effects, the expansion of nuclear facilities and activities, the development of related technologies, the progress of social factors, globalization and autonomization. On this basis, the changes and stage characteristics of the above driving forces were preliminarily analyzed; strategic research agendas (SRAs) of international organizations and several countries and regions in the field of radiation protection were briefly reviewed. Based on the above mentioned driving forces, the opportunities and challenges for domestic radiation protection discipline were preliminarily analyzed and discussed, which is for academic reference and comments. Reference | Related Articles | Metrics

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Research on hydrothermal method for stable treatment of free cesium in wastewater YU Weiyue, GAO Kai, WANG Hao, TAN Jun, YANG Biao, LIN Haipeng RADIATION PROTECTION    2025, 45 (2): 175-181.   Abstract （80）      PDF（pc） （6444KB）（62）       Knowledge map    Save Cesium is easily soluble in water, and has a good migration rate and a low boiling point, making it difficult to dispose of safely. The safe disposal of radioactive cesium is an urgent problem to be solved. Current technologies used for cement fixation and solidification, and ion exchange have certain shortcomings in the treatment of cesium containing waste liquid, and further optimization is urgently needed. Pollucite belongs to the zeolite type molecular sieve, with a suitable pore size. Without damaging the structure of pollucite, radioactive cesium cannot diffuse out of it. Many studies have shown that it is one of the potential ultimate choices for disposing of radioactive cesium. In previous studies, pollucite needs to be synthesized at high temperatures above 1 000 ℃, which can cause the volatilization of cesium and increase the difficulty of tail gas treatment. This study used hydrothermal method to simulate the generation environment of molecular sieve zeolites in nature and achieved the synthesis of pollucite at lower temperatures. Through a 2 L/batch treatment device, the cesium containing waste liquid is treated, with a removal rate of over 99% for cesium in the wastewater. This study also tested the leaching resistance, thermal stability, and radiation resistance of cesium, confirming its strong stability and suitability as a radioactive disposal material. Reference | Related Articles | Metrics

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Study on basic construction of quality assurance platform for radiation monitoring YANG Youkun, BAO Li, WANG Ruijun, LIAN Bing, SONG Qinnan, LI Pengxiang, MA Xuyuan RADIATION PROTECTION    2025, 45 (3): 207-213.   Abstract （78）      PDF（pc） （1702KB）（90）       Knowledge map    Save This study conducts an investigation into the current status of radiation monitoring and its quality assurance both domestically and internationally. This study identifies shortcomings in the quality assurance efforts within the field of radiation monitoring in China and proposes the establishment of a radiation monitoring quality assurance platform in China. This study also outlines the technical architecture for the construction of this platform and conducts in-depth research on its foundational infrastructure. The establishment of a framework structure with “one core, four supporting pillars” as the foundational infrastructure of the quality assurance platform was proposed. Through technological innovation and optimization, the study aims to strengthen the connection between the core and external interfaces, thereby ensuring the effective operation of the platform’s foundational infrastructure. This lays a solid foundation for subsequent iterations and upgrades of the quality assurance platform, facilitating effective quality assurance efforts in the field of radiation monitoring. Reference | Related Articles | Metrics

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Study on the removal of Co2+ in waste water by different adsorption materials ZHANG Huiwei, HE Xiaoping, LIU Yusen, CHEN Yizhi, ZHANG Peng, LIN Mingzhang RADIATION PROTECTION    2025, 45 (2): 108-118.   Abstract （76）      PDF（pc） （1090KB）（115）       Knowledge map    Save Radioactive cobalt (Co) is the main nuclide among the radioactive nuclides produced in the primary loop of nuclear power plants and it will be transferred to the decontamination liquid after the decontamination of the primary loop pipeline. By investigating the adsorption materials of Co2+, the adsorption effect of different adsorption materials was compared and analyzed, and the performance of different adsorption materials was clarified, which provided a basis for the research of absorption materials for Co2+ in waste water. The results showed that: the adsorption capacity of minerals and biological adsorbents was small; metal oxides did not show adsorption performance under acidic conditions; the adsorption rate of ion exchange resin was slow; activated carbon had both fast adsorption rate and high adsorption, but it could not show good adsorption performance under acidic conditions, and the research of other carbon materials was still in the laboratory stage. In view of the above, it is suggested to use inorganic nanometer materials with strong stability, boron nitride and graphene oxide, as the base material to synthesize materials with level pore structure, and to carry out functional modification on this basis, so as to synthesize adsorption materials with high adsorption performance under harsh conditions such as or strong acid. Reference | Related Articles | Metrics

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Measurement of ultra-trace level 239Pu in seawater samples by accelerator mass spectrometry WU Mengmeng, YIN Yunyun, GUO Luzhen, LV Tianlin, WANG Chuangao, PANG Hongchao RADIATION PROTECTION    2025, 45 (2): 133-140.   Abstract （72）      PDF（pc） （8160KB）（43）       Knowledge map    Save 239Pu in seawater was measured by accelerator mass spectrometry (AMS) system independently developed by China Institute of Atomic Energy. The 239Pu in seawater samples was separated and purified by anion resin, and the target samples were prepared by ferric hydroxide co-precipitation method. A set of tap water samples was prepared as blank samples to evaluate the measurement method with a detection limit of 0.9 fg (2.0 μBq). By this method, 239Pu in seawater samples was measured and analyzed. And the uncertainty of the measurement method was analyzed. Reference | Related Articles | Metrics

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The study of wind tunnel experiment on the radioactive material transmission in small scale with building and terrain ZHANG Fang, FAN Dan, GUO Zhanjie, LV Minghua, HUANG Sha, LI Yunpeng, ZHANG Junfang RADIATION PROTECTION    2025, 45 (2): 149-156.   Abstract （71）      PDF（pc） （9378KB）（37）       Knowledge map    Save A wind tunnel experimental study was performed in small scale for representative nuclear power plant site. The influence of buildings and terrain to radioactive material diffusion in the near field was studied. The model rate is 1∶600, and the similar demand of model and physical prototype is satisfied by correcting profile of wind and turbulence. 6 wind directions were studied for disturbing of building and terrain to horizontal and vertical flow field under condition of the annual average wind speed and light wind speed. The experimental results show that the wind speed is deficit and turbulence intensity is improved in WNW to ESE axis wind direction. The different sample sites have different impact to wind speed and turbulence intensity. The distribution of stack emission and ground-level emission in ground axis were different in the condition of annual mean wind speed and light wind speed. The axial maximum diffusion factor is 4.05×10-5 s/m3 under stack emission condition, and the distance presented is 240 m. The axial maximum diffusion factor is 4.79×10-3 s/m3 under ground emission condition, and the distance presented is 45 m. Reference | Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (3): 0-0.   Abstract （71）      PDF（pc） （199KB）（65）       Knowledge map    Save Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (2): 0-0.   Abstract （69）      PDF（pc） （172KB）（54）       Knowledge map    Save Related Articles | Metrics

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Quantitative analysis of the correlation between regional electromagnetic levels and population density based on vehicle survey XU Hui, KANG Xiaohan, TONG Jing, LI Fei RADIATION PROTECTION    2025, 45 (2): 141-148.   Abstract （65）      PDF（pc） （7580KB）（40）       Knowledge map    Save In this paper, a 30 MHz to 6 GHz EMF vehicle survey was carried out in two administrative districts of Beijing. More than 1.33 million data records of electric field intensity were obtained, which were fell into 22 subdistricts and towns in each of the two administrative districts based on geographical location information. The average RF total value was calculated. The average ranges are (0.43-1.67) V/m, (0.56-1.51) V/m respectively; The correlation coefficients with the population density and base station density of each subdistricts and towns are all higher than 0.8, indicating a strong positive correlation. On the other hand, a 24 hour 30 MHz to 6 GHz vehicle survey was carried out in a business district of Beijing, and the total RF value and base station RF value of 24 groups with a total of more than 145,000 points were obtained. The measured values ranged from (0.70-1.46) V/m and (0.67-1.31) V/m, respectively; The hourly population density was calculated by analyzing the heat map of Baidu population flow, which ranged from (6.58-46.54) human/hm2. It is found that the correlation coefficients between hourly population density and hourly RF and base station RF values are as high as 0.901. Obviously, the regional electromagnetic level is strongly correlated with the spatial distribution of population density and the 24 hour fluctuation of regional electromagnetic level is strongly correlated with the variation trend of population flow concentration density. Reference | Related Articles | Metrics

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Harmonizing the development of radiation protection standards with radiation therapy equipment and technology WANG Hongkai, TIAN Yuan, DAI Jianrong RADIATION PROTECTION    2025, 45 (3): 214-220.   Abstract （64）      PDF（pc） （2086KB）（196）       Knowledge map    Save This study analyzes the recent advancements in radiation therapy equipment technology, focusing on medical linear accelerators, conformal intensity-modulated radiation therapy technology, proton and heavy ion therapy equipment, as well as new mobile radiation therapy devices and high-dose-rate therapy modes. The study highlights the challenges in aligning the development of radiation therapy technologies with existing radiation protection standards. The analysis result indicates that the growth and application of certain new technologies are constrained by current radiation protection standards. Specifically, the use of the instantaneous maximum ambient dose equivalent rate as a criterion for evaluating radiation therapy rooms is inconsistent with real working conditions, making it difficult to control personnel exposure based on variations in dwell time and workload. This can lead to a significant increase in construction costs for shielding design. Furthermore, the current standards do not adequately account for changes in beam angles associated with new technologies, and the conditions for maximum field size and dose rate measurement do not accurately align with clinical practices. Based on this analysis, it is recommended that the current radiation protection standards for radiation therapy should be revised to replace the traditional evaluation criterion with the time-averaged maximum ambient dose equivalent rate. Additionally, relevant parameters and conditions should be optimized to better accommodate the evolving needs of modern radiation therapy equipment. By updating and refining existing radiation protection standards, the safety of radiation therapy can be better ensured while fostering the adoption of new radiation therapy technologies, ultimately achieving a harmonious development of radiation protection standards and radiation therapy equipment technology. Reference | Related Articles | Metrics

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Analysis on neutron dose at proton FLASH therapy room LI Kundong, ZHANG Haiyang, JIA Meichao, XIAO Jie RADIATION PROTECTION    2025, 45 (3): 285-291.   Abstract （59）      PDF（pc） （4737KB）（67）       Knowledge map    Save The distribution of secondary neutrons in the water model under the condition of ultra-high dose rate proton beam (FLASH ) is calculated by Monte Carlo method. The calculation results show that the distribution of neutrons produced by the indoor energy degrader in the water phantom can reach ten times of that without the degrader when the proton energy is from 70 to 116 MeV. In the case of low proton energy, the cumulative neutron dose of one treatment can reach more than 200 mGy. Reference | Related Articles | Metrics

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Analysis of the current status and optimization suggestions for radioactive liquid waste treatment system of the M310 NPP SI Pengkun RADIATION PROTECTION    2025, 45 (2): 167-174.   Abstract （57）      PDF（pc） （2384KB）（84）       Knowledge map    Save M310 reactor units are the earliest Nuclear Power Units introduced in China. Although their radioactive wastewater treatment systems are operating stably, they face challenges such as high operating costs, unstable efficiency, low decontamination factors, and high solid waste output, etc. In particular the low decontamination factors, current processes and equipment are no longer able to meet the demand for further reducing the total amount of radioactive nuclides emitted into the environment. There is still a considerable gap compared to advanced countries and regions. This paper summarizes the current operational status and considers the mature and advanced wastewater treatment technologies at home and abroad, with the aim to elaborate the optimization direction and suggestions for the radioactive wastewater treatment system of M310 Nuclear Power Units. Reference | Related Articles | Metrics

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Radiation environment remediation and long-term management effect evaluation of a decommissioned uranium mine and mill facility in Southwest China BI Cunde RADIATION PROTECTION    2025, 45 (3): 229-236.   Abstract （56）      PDF（pc） （2217KB）（22）       Knowledge map    Save The decommissioning environmental remediation and management of uranium mine and mill facility is a complex system engineering. Taking a uranium mining and mill facility in Southwest China as an example, this paper reviews the process of decommissioning, the engineering measures in decommissioning, and the long-term management after decommissioning. The results of important radiation environment monitoring indicators over the years were tracked, and the effectiveness of various measures during decommissioning was reviewed and evaluated. Reference | Related Articles | Metrics

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Several viewpoints on medium-depth disposal of radioactive waste LI Feng, WANG Hongzu, ZHU Jie, ZHANG Xue RADIATION PROTECTION    2025, 45 (3): 273-278.   Abstract （56）      PDF（pc） （1183KB）（59）       Knowledge map    Save Considering the concept on medium-depth disposal of intermediate level radioactive waste proposed by the International Atomic Energy Agency, this paper surveyed the disposal methods of radioactive waste in some major nuclear countries, analyzed the current status of waste disposal in countries that have carried out intermediate-level disposal, combined the trend of nuclear energy development in China, and estimated the amount of intermediate-level waste that China need to be disposed of in 2030 (3 400 m3), 2050 (28 700 m3), and the latter half of this century (49 400 m3, excluding the intermediate-level waste generated from the operation of nuclear fuel cycle facilities). This paper also briefly analyzed the economic feasibility of disposal and concluded that there is an effective disposal demand in the near future, suggesting that China should proceed with the scientific research, standardization, and early-stage engineering work on intermediate-level waste disposal in an orderly manner as soon as possible. Reference | Related Articles | Metrics

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Analysis of MRI integrated diagnostic and therapeutic equipment shielding technology WANG Xiaowa RADIATION PROTECTION    2025, 45 (3): 292-298.   Abstract （55）      PDF（pc） （1995KB）（204）       Knowledge map    Save Magnetic Resonance Imaging (MRI) is a pivotal technology in modern medical diagnostics, renowned for its high resolution and excellent contrast of soft tissues. In recent years, the integration of MRI technology with other diagnostic and therapeutic devices, such as Positron Emission Tomography (PET), Single Photon Emission Computed Tomography (SPECT), Electrocardiography (ECG), Electroencephalography (EEG), and radiation therapy equipment like linear accelerators and proton therapy accelerators, has significantly enhanced the precision and efficiency of diagnostics and treatments. This paper discusses the shielding design and requirements for these integrated technologies, including technical aspects of magnetic and radiation shielding, as well as methodological approaches for both the equipment’s own shielding and the shielding of the room environment. This paper also introduces the shielding requirements and influencing factors for the integrated equipment itself, and also proposes that the shielding technology for integrated equipment is not a simple “1+1” model of magnetic shielding plus radiation shielding, but rather some certain synergistic effect involved. Reference | Related Articles | Metrics

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Research on evolution of swelling performance of buffer barrier in high-level radioactive waste repository based on machine learning algorithms ZHANG Ming, HU Dongke, XIE Jingli, WANG Zhaoming, LI Xiaoming, ZHOU Fangliang, ZHAO Liuyi RADIATION PROTECTION    2025, 45 (2): 157-166.   Abstract （52）      PDF（pc） （6209KB）（59）       Knowledge map    Save High-level radioactive waste repository has a long service period and complex geological conditions. It is difficult for general tests to obtain the evolution trend of the swelling performance of bentonite buffer barrier under the working conditions of the repository. This paper attempts to use machine learning algorithms to research it. The model is trained by ten machine learning algorithms which is more mature in material performance prediction, the coefficient of determination and root mean square error of the above algorithms are compared and analyzed. The feasibility of machine learning algorithms in predicting the swelling performance of bentonite is discussed, and the neural network algorithm is selected as the best one. The geochemical condition of Beishan candidate repository in China is introduced. It is predicted that the swelling pressure evolution trend of Gaomiaozi bentonite during the service of high-level radioactive repository is ‘S’ type. The results show that considering the influence of dry density, montmorillonite content, initial moisture content and temperature, the recommended value of initial dry density of buffer barrier is not less than 1.58 g/cm3. If the effect of Fe(II) release from the iron container is further considered, the initial dry density of the buffer barrier should be further increased. This study can provide a theoretical basis for the in-situ experiment and buffer barrier performance evaluation of the underground laboratory of Beishan high-level waste radioactive repository in China. Reference | Related Articles | Metrics

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Ion irradiation effects of Mg1-xZnxAl2O4 (x = 0-1) spinels CHEN Shuangqiang RADIATION PROTECTION    2025, 45 (3): 242-251.   Abstract （50）      PDF（pc） （8723KB）（18）       Knowledge map    Save Spinels have been proposed for a multitude of nuclear-energy-related applications, including as nuclear waste forms, inert matrix fuels and structure materials for nuclear reactor, due to its excellent mechanical properties, chemical durability and radiation resistance. The study of radiation behavior and radiation tolerance have important significance in materials selection, assessment and modification. The 500 keV He ions irradiation were performed on Mg1-xZnxAl2O4 (x = 0-1) spinels at room temperature with different ion fluence. There were a phase transition from order spinel to disorder spinel (O-D) but no amorphization in all of the samples even if the highest ion fluence1×1017 ions/cm2 according to the results of grazing incidence X-ray diffraction and Raman scattering spectrum (Raman). The swelling ratio of MgAl2O4, Mg0.4Zn0.6Al2O4 and ZnAl2O4 caused by irradiation is 0.43％, 0.12％and 0.67％, respectively. We think Mg0.4Zn0.6Al2O4 spinel have the best radiation swelling tolerance, closely followed by MgAl2O4 and ZnAl2O4 is the worst when the ion fluenceis below 1×1017 ions/cm2. But, maybe the swelling ratio of Mg0.4Zn0.6Al2O4 will outstrip MgAl2O4 at the higher ion fluence than 1×1017 ions/cm2. Reference | Related Articles | Metrics

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Trend and analysis of changes in radiation environment levels of urban radioactive waste storage facilities in Guangxi from 2013 to 2022 WU Yichao, TIAN Yu, LIU Jing, LI Runhua, LIANG Xiaoxu, YUAN Hairong RADIATION PROTECTION    2025, 45 (3): 237-241.   Abstract （48）      PDF（pc） （1061KB）（59）       Knowledge map    Save Through the analysis of the monitoring data of the radiation environment quality of the urban radioactive waste repository in Guangxi from 2013 to 2022, the variation pattern of the radiation environment quality in the storage area in the past ten years is summarized, which provides a scientific basis for future radiation supervision. The analysis and monitoring results show that the ambient dose rate of γ radiation air in Guangxi urban radioactive waste repository from 2013 to 2022 is within the natural background range in Guangxi. The total α and total β radioactivity concentrations in water were lower than the national guidance values. The contents of radionuclides in soil and aerosol are within the natural background range in Guangxi. The urban radioactive waste repository in Guangxi is in good condition. The air, water and soil are not polluted by artificial radionuclides, and the radiation is safe and controllable. Reference | Related Articles | Metrics

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Components and bioinformatics analysis of adenovirus vector of the PprI gene of deinococcus radiodurans WANG Zhipeng, ZHAO Lu, LI Jianhua, LIU Huan, CHEN Jianhua RADIATION PROTECTION    2025, 45 (2): 182-188.   Abstract （44）      PDF（pc） （8986KB）（11）       Knowledge map    Save PprI gene has obvious prevention and control effect on acute radiation damage caused by neutron and gamma rays in mammals. In this study, the PprI gene was directed cloned into the shuttle plasmid pADV-mCMV-MCS-3xFLAG using the non-replicating adenovirus vector system AdMax packaging system, and then co-transfected into HEK293 cells with the adenovirus skeleton plasmid for homologous recombination. The recombinant adenovirus pAdMax-PprI was obtained and identified. The PprI protein was bioinformatics analyzed. PCR results of recombinant adenovirus pAdMax-PprI showed that the inserted fragment was consistent with the size of the PprI gene fragment, and sequencing showed that the inserted fragment was consistent with the PprI gene sequence. Western blot results showed that PprI protein was immunogenic with a molecular weight of about 45 kDa. Bioinformatics analysis showed that PprI gene encodes a hydrophilic protein composed of 163 amino acid residues, which exists in cell membrane, has no signal peptide and transmembrane structure, and has 5 antigenic epitopes. The secondary structure includes three forms of random curling, α-helix and β-folding. Random curl (46.73%) and α helix (28.83%) were the main structures. The prediction results of tertiary structure were consistent with those of secondary structure. The results laid a foundation for further studies on the function of PprI and its radiation resistance. Reference | Related Articles | Metrics

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Analysis of lens opacification status and influencing factors among radiological workers in China’s nuclear power plants WANG Huaxian RADIATION PROTECTION    2025, 45 (3): 266-272.   Abstract （44）      PDF（pc） （980KB）（136）       Knowledge map    Save This study aims to investigate the status of lens opacification and its influencing factors among radiological workers in China’s nuclear power plants, with the expectation of providing a scientific basis for the occupational health surveillance and radiation protection of this population. The study selected 2,091 radiological workers from nuclear power plants and 1,500 non-radiological workers in 2023. Analysis was conducted through questionnaire surveys and lens examinations. The results showed that the rate of lens opacification in the radiological group was significantly higher than that in the non-radiological group. Factors such as gender, age, annual effective dose per capita, job type, organizaation, and daily sleep duration during workdays significantly affected lens opacification. This study indicates that there is a certain correlation between long-term exposure to low-dose ionizing radiation and lens opacification, where gender, age, annual effective dose per capita, job type, and workplace are independent risk factors for the occurrence of lens opacification, while daily sleep duration during workdays is a protective factor. These findings are of certain significance for formulating occupational health surveillance strategies for radiological workers in nuclear power plants. Reference | Related Articles | Metrics

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Numerical simulation study on the influence of high-rise buildings on pollutant dispersion under stable stratification LI Jixun RADIATION PROTECTION    2025, 45 (3): 252-265.   Abstract （41）      PDF（pc） （15460KB）（10）       Knowledge map    Save The influence of stable stratification with different Richardson numbers (Rib) on the flow structure and pollutant dispersion around a 1∶1∶2 (length∶width∶height) high-rise building using the k-epsilon high Reynolds number turbulence model was simulated. The results show that the temperature stratification significantly affects the flow structure around the building. As Rib increases, the leeward stagnation point gradually moves towards the top of the building, the recirculation region on the top of the building shifts backward, and the length of the recirculation region on the windward side of the building first increases and then decreases. The vortex position gradually moves above the building. The high TKE/uH2 region around the building is mainly distributed on the top of the building and in the downwind recirculation region. As Rib increases, the TKE/uH2 decreases in the top and wake regions of the building. With increasing Rib, the ground-level pollutant concentration first increases and then decreases, the height of the downwind plume gradually decreases, and the maximum concentration in the plume rises. Reference | Related Articles | Metrics

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Study on the ultrasonic enhanced recovery of membrane flux in the treatment of uranium-containing decontamination wastewater GUO Lixiao RADIATION PROTECTION    2025, 45 (3): 279-284.   Abstract （41）      PDF（pc） （3731KB）（42）       Knowledge map    Save Considering the characteristics of uranium decontamination wastewater, such as high surfactant content, radioactivity and complicated component, this study used ultrasonic enhanced membrane separation technology to treat the uranium decontamination wastewater. This study explored the cleaning effects of ultrasonic working time, ultrasonic frequency, membrane contamination time and other factors on the flux of the ceramic membrane, and analyzed the comparison result with the traditional cleaning technology. The results show the cleaning effect is better when the ceramic membrane pore size is 0.2 μm, ultrasonic time is 6 min, and ultrasonic frequency is 35 kHz. Ultrasonic enhanced membrane cleaning technology for different levels of contaminaed ceramic membrane flux can be restored to the original flux of 70%-95% and has obvious advantages compared with the ordinary rinsing technology. The ultrasonic cleaning effect of water rinsing can be enhanced to more than 30% for low concentration, and can still be enhanced by about 15% for high concentration. The membrane flux can be enhanced by 15%-30%. In conclusion, the ultrasonic enhanced ceramic membrane can effectively carry out the treatment of uranium-containing decontamination wastewater, enhance the membrane flux and reduce membrane contamination, which has good prospects for application. Reference | Related Articles | Metrics

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Research on assessment method and software development for core damage of sodium cooled fast reactor LIANG Boning, JIA Linsheng, YANG Yapeng, FENG Zongyang, WANG Ning, LIU Zhe RADIATION PROTECTION    2025, 45 (3): 299-304.   Abstract （40）      PDF（pc） （1020KB）（98）       Knowledge map    Save On the basis of core damage assessment method for PWR and combined with the characteristics of 600 MW demonstration sodium cooled fast reactor, this paper proposes an assessment model for core damage of sodium cooled fast reactor based on the comprehensive assessment of on-line monitoring instrument readings as the main model while the radionuclides sampling assessment as the auxiliary model. The developed software of core damage assessment for sodium cooled fast reactor has been applied to the 600 MW demonstration sodium cooled fast reactor project. Reference | Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (2): 196-196.   Abstract （40）      PDF（pc） （576KB）（20）       Knowledge map    Save Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (2): 191-196.   Abstract （39）      PDF（pc） （752KB）（19）       Knowledge map    Save Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (2): 140-140.   Abstract （38）      PDF（pc） （594KB）（7）       Knowledge map    Save Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (2): 181-181.   Abstract （36）      PDF（pc） （573KB）（23）       Knowledge map    Save Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (2): 174-174.   Abstract （36）      PDF（pc） （596KB）（13）       Knowledge map    Save Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (3): 228-228.   Abstract （35）      PDF（pc） （590KB）（5）       Knowledge map    Save Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (3): 305-309.   Abstract （33）      PDF（pc） （612KB）（8）       Knowledge map    Save Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (3): 206-206.   Abstract （33）      PDF（pc） （590KB）（5）       Knowledge map    Save Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (2): 189-191.   Abstract （32）      PDF（pc） （556KB）（10）       Knowledge map    Save Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (3): 265-265.   Abstract （30）      PDF（pc） （607KB）（11）       Knowledge map    Save Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (3): 251-251.   Abstract （28）      PDF（pc） （590KB）（9）       Knowledge map    Save Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (3): 310-312.   Abstract （28）      PDF（pc） （524KB）（6）       Knowledge map    Save Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (3): 291-291.   Abstract （28）      PDF（pc） （591KB）（13）       Knowledge map    Save Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (6): 0-0.   Abstract （21）      PDF（pc） （188KB）（8）       Knowledge map    Save Related Articles | Metrics

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The evolution and update prospects of the four generations of basic standards for radiological protection in China ZHENG Junzheng RADIATION PROTECTION    2025, 45 (6): 545-557.   Abstract （19）      PDF（pc） （8821KB）（10）       Knowledge map    Save This article briefly discusses the pivotal role of the basic standards for radiological protection in promoting the development of radiological protection related disciplines. Radiological protection system outlined in the recommendations published by the International Commission on Radiological Protection (ICRP), which provide basis for developing radiological protection standards, has undergone four generations of evolution; And the International Basic Safety Standards(IBSS), jointly developed by the International Atomic Energy Agency(IAEA) and multiple international organizations, has completed three generations of evolution. This paper focuses on the main characteristics of the four generations of evolution of basic standards for radiological protection in China, including 1960, 1974, 1980s and 2002. Based on the more than 8 years experience in joint development of the fourth generation basic standard GB 18871—2002, valuable lessons need to be sorted out; It will be beneficial to continuously update the basic standards of radiological protection and develop the discipline of radiological protection. As a participant in the development of China’s third and fourth generation basic standards, I would like to put forward six suggestions for updating the standards and promoting the fifth generation basic standards to meet the urgent needs of related development in China. Obviously, it is imperative to develop new basic standards that are scientifically sound, easy to implement, and able to solve practical problems in a targeted manner, based on national conditions and international standards. Reference | Related Articles | Metrics

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Correlation analysis of effluent discharge limits and the power of nuclear power plants HUANG Yanjun, ZHAO Feng, SHANGGUAN Zhihong RADIATION PROTECTION    2025, 45 (6): 558-563.   Abstract （17）      PDF（pc） （3467KB）（4）       Knowledge map    Save Controlling of effluent discharge is a major aspect of environmental radiation protection in nuclear power plants (NPP). The national standard GB 6249—2011 set the discharge limits for a single unit with thermal power 3 000 MWt and clarified that the discharge control values for other power reactors should be appropriately adjusted. Currently, various types of reactors, technologies, standards, and multiple countries import coexist in China, resulting in a significant difference in the thermal power of nuclear power units. How to determine their discharge limits has become a focus for the environmental radiation protection management of NPPs. This paper collects data on the design and approval of effluent discharge in domestic nuclear power plants, as well as domestic and foreign data on effluent discharge, design power, and electricity generation, and conducts the correlation analysis. This paper proposes methods and suggestions for adjusting the discharge control values according to unit power, providing a reference for the standardized management of effluent discharge for NPPs. Reference | Related Articles | Metrics

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Research and optimization on flexible perovskite X/γ radiation detection materials WANG Maoling, LIU Xinmei, SHI Zhongyan, LI Haojin, ZHANG Jing, LINGHU Renjing, HUANG Jian, LIU Xin, LIU Zhaoxing, JIN Haijing, WANG Jia, ZHAO Ri, ZHAO Kui RADIATION PROTECTION    2025, 45 (6): 564-575.   Abstract （13）      PDF（pc） （12211KB）（4）       Knowledge map    Save Traditional solid detectors such as scintillators and semiconductors are difficult to meet the future requirements for flexible radiation detection applications. Therefore, in this paper, a new technology route is proposed based on novel perovskite materials. The perovskite solution is filled into the flexible matrix of porous nylon film, and the flexible detection materials are prepared through recrystallization. Scanning electron microscopy imaging, X-ray diffraction, ultraviolet absorption spectroscopy, and tests such as μτ value, dose rate linearity, and detection sensitivity under X-ray irradiation are conducted on six prepared materials. The six materials are optimized and further X-ray and γ-ray tests are carried out. The results show that the μτ value of [NH3(CH2)4NH3]BiI5 flexible film material is 1.30×10-3 cm2·V-1; the optical band gap is 2.02 eV: and the detection sensitivity is (3 190±50)μC·Gyair-1·cm-2, which is superior to existing semiconductor detectors and retains the inherent excellent detection characteristics of perovskite crystal materials. This paper lays an important foundation for the subsequent research and development of flexible radiation detectors and detection systems. Reference | Related Articles | Metrics

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Design and optimization of a multi-imaging plate detector for BNCT beam parameter measurement JIADELA Kuanibieke, ZHAO Ri, LI Deyuan, YAN Xuewen, CHEN Faguo, QIAO Zhaopeng, ZHANG Pengpeng, ZHANG Ke RADIATION PROTECTION    2025, 45 (6): 609-618.   Abstract （13）      PDF（pc） （3251KB）（3）       Knowledge map    Save The beam quality of Boron Neutron Capture Therapy (BNCT) is a crucial factor affecting its therapeutic efficacy. In recent years, multi-imaging plate systems have attracted increasing attention for measuring BNCT beam parameters. In such systems, the thickness of the conversion layers plays a key role in determining measurement accuracy. This study applies a particle swarm optimization algorithm to optimize the conversion layer thicknesses. A Monte Carlo simulation is used to calculate the system’s response matrix at each step of iteration. The condition number of the response matrix is chosen as the optimization objective. Through iterative computations, the optimal thickness values are obtained. Based on these results, a physical interpretation is further provided, focusing on the range of secondary charged particles and the enhancement effects of the conversion layers on each imaging plate. The research findings offer important reference data for the development of multi-imaging plate detectors for BNCT beam characterization. Reference | Related Articles | Metrics

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Investigation of the effects of gamma-ray energy, coded aperture mask and detector thickness on the fully coded field of view WANG Yilin, LIANG Xiuzuo, LIU Xinmeng, YU Xiaodong, GAO Ge, YANG Yao, SHUAI Lei RADIATION PROTECTION    2025, 45 (6): 576-585.   Abstract （12）      PDF（pc） （12430KB）（4）       Knowledge map    Save In coded aperture imaging systems, the field of view (FOV) is conventionally determined by the geometric relationship between the coded aperture mask and the position-sensitive detector. However, the influence mechanism of critical physical parameters—including the thickness and material properties of both the mask and detector, as well as the radiation energy—on the fully coded field of view (FCFOV) has not been systematically investigated. This study employs a controlled-variable approach to systematically elucidate the relationship among these parameters (mask thickness/material, detector thickness/material, and energy) and the FCFOV. By introducing the concept of equivalent thickness to revise the conventional geometric model (which relies solely on mask-detector distance), we propose an empirical parameterized formula for FCFOV calculation, representing the first such model of its kind internationally. Both simulations and experimental results validate the effectiveness of the formula, demonstrating its superior accuracy in defining the FCFOV boundaries compared to traditional methods. These research findings provide a important reference for future FOV calibration and system design in coded aperture imaging applications. Reference | Related Articles | Metrics

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Investigation and evaluation of Polonium-210 content in tobacco XIAO Peng, ZHENG Xiaojing RADIATION PROTECTION    2025, 45 (6): 603-608.   Abstract （11）      PDF（pc） （1107KB）（4）       Knowledge map    Save Tobacco leaves contain various natural radioactive nuclides, smoking may increase internal radiation dose to the human body. This paper analyzed the 210Po levels in 36 domestic cigarette brands and 4 foreign cigarette brands. The analysis results showed that the 210Po content in domestic cigarettes ranged from 22.3 to 48.6 mBq/g (or 13.1 to 29.9 mBq per cigarette), with an average of 32.9 mBq/g (or 20.2 mBq per cigarette); while in foreign cigarettes, 210Po content ranged from 18.5 to 24.3 mBq/g (or 11.1 to 12.7 mBq per cigarette), with an average of 21.2 mBq/g (or 12.1 mBq per cigarette). Overall, the 210Po content in domestic cigarettes was slightly higher than that in foreign cigarettes. Based on the 210Po content in tobacco shreds, it was estimated that the amount of 210Po inhaled by Chinese smokers from cigarettes was approximately from 24.85 to 150.29 mBq per day, and the internal radiation equivalent dose to the lung tissue was from 27.48 to 166.22 μSv per year. Reference | Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (6): 575-575.   Abstract （11）      PDF（pc） （643KB）（3）       Knowledge map    Save Related Articles | Metrics

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RADIATION PROTECTION    2025, 45 (6): 637-637.   Abstract （11）      PDF（pc） （628KB）（0）       Knowledge map    Save Related Articles | Metrics

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Photo-oxidation aerosol conversion of I-129 in gaseous effluent from reprocessing plants LIN Yibo, LUO Zhiping, WANG Chuangao, CHEN Ran RADIATION PROTECTION    2025, 45 (6): 586-594.   Abstract （10）      PDF（pc） （3058KB）（1）       Knowledge map    Save I-129 is a typical emission nuclide in the gaseous effluent of spent fuel reprocessing, which will produce certain radiation hazards to the environment and human body. Therefore I-129 needs to be monitored. Until now online monitoring of I-129 in the gaseous effluent of spent fuel reprocessing plant is still vacant in China. Based on the existing aerosol online monitoring system, this paper designs an aerosol conversion device to solve the sampling problem of the aerosol online monitoring system, and provides a pre-sampling device and method for the online monitoring of gaseous I-129 in the gaseous effluent of the reprocessing plant by the subsequent linkage aerosol online monitoring technology. The aerosol conversion experiment was carried out by stable iodine instead of I-129, and the conversion efficiency of the device was measured under different conditions. Combined with the performance parameters of ICP-MS, the conversion efficiency of the aerosol conversion device and the loss rate of aerosol during the online monitoring process, the low detection limit range of the aerosol conversion device for the online monitoring of I-129 in gaseous effluent was preliminarily derived, which was compared with that of the international continuous monitoring low detection limit requirements. The preliminary low detection limit range of the aerosol conversion device for online monitoring of I-129 in gaseous effluent was compared with the international continuous monitoring low detection limit requirements, which verified the feasibility of the method and the better prospect and research value in the field of online monitoring of I-129 in reprocessed gaseous effluent. Reference | Related Articles | Metrics

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Emergency support mechanism among nuclear power groups for nuclear accidents HUANG Xiaohang, HAN Min, SUN Zhigang, CHEN Rong, YANG Yan, LU Yinjuan, JI Yunzhe, HUANG Shaoqing, ZHANG Dingwen, ZHU Yuelong, GOU Quanlu, BAO Yuzhen RADIATION PROTECTION    2025, 45 (6): 619-629.   Abstract （10）      PDF（pc） （8804KB）（2）       Knowledge map    Save When nuclear power plants experience severe accidents triggered by external event or catastrophic natural disasters beyond design basis accident, there is a need for off-site emergency response forces to provide support. The mutual support among nuclear power groups serves as an important backup force. Based on the analysis of the emergency response capabilities layout among domestic nuclear power groups and drawing from the practices of international support for nuclear accident emergency in other countries, this paper identifies current issues in inter-group emergency support for nuclear accident. This paper also explores comprehensive considerations necessary for implementing mutual support among groups, coordination and cooperation with national-level nuclear emergency support forces, and requirements for routine maintenance of the support mechanism. Relevant suggestions are proposed. Reference | Related Articles | Metrics