Objective: To investigate the gross α and gross β radioactivity in Dongjiang River during high and low flow periods in Dongguan City, China, and evaluate the radiation safety status of Dongjiang River as a source of drinking water. Methods: The gross α and gross β radioactivity levels were measured in the source water, treated water, and tap water from eight water treatment plants along the Dongjiang River, which relied on Dongjiang River water as their source, during both high and low flow periods. The annual internal effective dose from consuming Dongjiang River water was estimated. Results: In high flow period, the gross α and gross β radioactivity levels were 0.016-0.041 and 0.063-0.140 Bq/L for source water, 0.011-0.039 and 0.064-0.131 Bq/L for treated water, and 0.013-0.024 and 0.078-0.127 Bq/L for tap water. In low flow period, the gross α and gross β radioactivity levels were 0.012-0.029 and 0.055-0.141 Bq/L for source water, 0.012-0.019 and 0.054-0.124 Bq/L for treated water, and 0.012-0.024 and 0.083-0.134 Bq/L for tap water. The estimated total effective doses of gross α and gross β radioactivity caused by consumption of water from Dongjiang River were 3.6 and 0.48 μSv/a, respectively. Conclusion: The gross α and gross β radioactivity levels of water from Dongjiang River in Dongguan City are below the radioactive indicator values specified in the Standards for Drinking Water Quality (GB 5749-2022), remaining within the range of natural environmental background. The annual internal effective dose caused by consumption of water from Dongjiang River is below the individual dose limit set in the Guidelines for Drinking Water Quality.

Objective: To investigate the current level of public awareness regarding nuclear emergency evacuation around a nuclear power plant, analyze the influencing factors, and propose suggestions and countermeasures based on the results. Methods: In July 2024, according to the survey protocol and questionnaire developed by the National Institute for Radiological Protection, Chinese Center for Disease Control and Prevention, a field-based centralized online questionnaire was administered. A total of 854 residents living near the nuclear power plant were included as survey participants. An analysis of variance was used to compare the impact of different factors on the public knowledge of nuclear radiation and awareness of nuclear emergency evacuation, while the chi-square test was employed to compare differences between groups. Results: A total of 854 questionnaires were collected in this study. The survey revealed that the levels of public knowledge about nuclear radiation and awareness of nuclear emergency evacuation around the power plant were relatively low, with average objective awareness rates of 51% and 47%, respectively. In terms of age, the 30-45 years old group had the highest average score, while the group aged 60 and above had the lowest. Regarding education level, the group with primary school education or below had the lowest average score, whereas those with junior college or undergraduate education scored the highest. The internet (73.7%) was the primary source of emergency information for the public, followed by television (61.7%). The majority of the public (85.0%) expressed trust in the government during evacuation and were willing to follow governmental evacuation arrangements. The main reason for this willingness was the belief that the government could provide sufficient emergency supplies. Conclusion: The surveyed population exhibited low levels of knowledge regarding nuclear radiation and awareness of nuclear emergency evacuation, with generally low awareness rates. Awareness levels were influenced by factors such as sex, age, educational background, and distance from the nuclear power plant. To enhance public awareness, it is necessary to strengthen science communication related to nuclear radiation and public protective actions in nuclear emergencies. Targeted dissemination strategies with high communication effectiveness, accessibility, and public acceptance should be adopted to gradually enhance public awareness of nuclear radiation and nuclear emergency protective actions.

Dose conversion coefficients connect radiation field quantities with the protection quantities and operational quantities. In radiation protection practice, it plays an important role in facilitating the conversion between various measurement values, enabling compliance with individual dose limits, and optimizing radiation protection strategies. During the conversion process, conversion coefficients are affected by the types of rays, irradiation geometries, and human tissues and organs. Notably, the continuous development of anthropomorphic digital phantoms has led to the constant updating of conversion coefficients and the broadening of their application fields. However, with the development of radiation protection theory, new challenges have emerged in the establishment of conversion coefficients. This paper provides a concise overview of these aspects, aiming to give readers a basic understanding of the significance, application, and challenges associated with the conversion coefficients. Such an understanding will facilitate the effective implementation of the newly released standard WS/T 830.

Objective: Emergency response to public health emergencies constitutes a vital component of the modernization of national governance systems and capacities, directly impacting national security, social stability, and public health. This study aims to analyze the key issues and research hotspots in the field of emergency response to public health emergencies, providing theoretical foundations and practical guidance for formulating scientific and effective emergency strategies and policies. Ultimately, it seeks to enhance the nation’s capability to respond to public health emergencies and safeguard public health. Methods: Using core journals indexed in the China National Knowledge Infrastructure (CNKI) database as the data source, 1094 journal articles in the field of emergency response to public health emergencies in China from 2003 to September 2024 were selected as the research sample. Citespace visualization software was employed to organize and analyze the research process in the field of emergency response to public health emergencies. Results: The current research in this field predominantly involves small-scale cooperation, and the research process can be divided into four stages. The research in the emerging stage mainly focuses on the themes of emergency mechanism and emergency management, the development stage mainly centers on the themes of emergency capacity improvement and system exploration, the outbreak stage emphasizes the themes of COVID-19 and epidemic prevention and control, and the sustainable development stage highlights collaborative governance and informatization. Conclusion: The COVID-19 pandemic has accelerated the development of research in this field. Currently, the field shows a continuous growth, with an increasing volume of publications. The focus of current research has shifted towards collaborative governance and the study of assessment tools, aiming to enhance the efficiency and effectiveness in responding to public health emergencies. Moreover, the field is advancing toward more systematic and comprehensive research. However, there is still a need to strengthen scientific communication and collaboration.

Objective: Ionization chamber detector is commonly used for direct and continuous measurement of tritium concentration in the air. However, the measurement sensitivity is low due to the limitations of weak current measurement technology. It is necessary to develop a proportional counter for measuring tritium in the air. Methods: This study involved the design of a proportional counter, considering various factors such as materials and structure. The stability, plateau curve, detection efficiency, and energy spectrum of the counter were tested. Results: The coefficient of variation of the proportional counter was 3.14%, which met the standard requirement of being less than 15%. The plateau length was 260 V and the plateau slope was 0.80%/100V, which met the requirement of being less than 1%/100V. The tritium detection efficiency reached 68.02%. The energy spectrum measurement indicated a significant difference between tritium signal generated by the proportional counter and background signal, and the distribution of tritium in the energy spectrum was more concentrated. The background counting rate during tritium gas activity measurement could be reduced through energy spectrum measurement. Conclusion: The proportional counter can provide a reference for the direct and continuous measurement of tritium in the air.

Objective: To explore and establish a technical pathway for size-specific dose estimate (SSDE) in pediatric CT patients of different age groups based on structured dose files and DICOM files, and to provide an effective method for precise monitoring of medical radiation exposure in pediatric CT scans. Methods: Structured radiation dose reports (SR files) for pediatric patients aged 15 and under, who underwent CT scans between January and December 2023, were exported from the hospital information system. Scanning parameters and dose information were extracted using specialized software, and SSDE was calculated based on the patient body size parameters. The data were grouped by age (0- < 1 year, 1- < 5 years, 5- < 10 years, and 10-15 years) for statistical analysis. Results: From January to December 2023, a total of 2706 pediatric CT scans were performed at the hospital, including 385 (14.23%) head scans, 1990 (73.54%) chest scans, 143 (5.28%) abdominal scans, 112 (4.14%) limb scans, and 76 (2.81%) other scans. The typical volume CT dose index (CTDI_vol) for head CT in the age groups of 0- < 1 year, 1- < 5 years, 5- < 10 years, and 10-15 years were 36.21, 35.29, 37.27, and 41.18 mGy, respectively; the corresponding SSDE values were 41.27, 32.82, 30.56, and 28.41 mGy, respectively. For chest CT scans, the typical CTDI_vol for the age groups of 1- < 5 years, 5- < 10 years, and 10-15 years were 1.91, 2.11, and 2.51 mGy, respectively; the corresponding SSDE values were 2.36, 2.21, and 3.50 mGy, respectively. For abdominal CT scans, the typical CTDI_vol for the age groups of 1- < 5 years, 5- < 10 years, and 10-15 years were 3.94, 4.33, and 6.26 mGy, respectively; the corresponding SSDE values were 5.77, 7.10, and 9.79 mGy, respectively. Conclusion: This study developed a technical pathway to estimate the medical radiation doses of pediatric CT patients of different ages based on structured dose files and DICOM files. The feasibility of this approach was validated using data collected over a one-year period.

Objective: With the increase in pet-owning households in China, veterinary clinics have increased at an annual rate of 19.86%. However, the management blind area that may exist in multi-department supervision has led to a significantly worse working environment of radiation workers in veterinary clinics than that of medical institutions. The purpose of this study was to understand the levels of occupational external exposure of radiation workers in veterinary clinics in China, analyze the occupational risks faced by radiation workers in veterinary clinics, contribute to the protection of the occupational health of radiation workers, and provide data and scientific basis for the formulation of national relevant regulations and standards. Methods: The individual dose monitoring data of radiation workers in selected veterinary clinics in 2022 were obtained from the National Individual Dose Registration System. Results: This study involved 1868 radiation workers from 1216 veterinary clinics in 28 provinces and municipalities in China. The maximum annual effective dose was 8.93 mSv, the annual collective dose was 536.77 man·mSv, the average annual effective dose was 0.29 mSv, and the median was 0.15 mSv. The largest proportion of individuals (94.5%) received a dose of less than 1.0 mSv, while 5.4% had doses ranging from 1.0 mSv to less than 5.0 mSv. For radiation workers with an annual effective dose of 1.0 mSv and above, the individual distribution ratio of radiation workers in veterinary clinics was significantly higher compared with those in medical institutions and industrial applications (P < 0.05). Conclusion: The levels of occupational external exposure of radiation workers in veterinary clinics meet the requirements of national standards. However, attention should still be paid to the radiation protection of radiation workers in veterinary clinics. This includes enhancing the responsibility awareness of veterinary clinic owners, strengthening protection training for radiation workers, protecting the occupational health of practitioners, and preventing the occurrence of occupational radiation diseases.

Objective: To analyze the distribution characteristics and trends of occupational exposure types of medical radiation workers in Gansu Province, China, and to provide a basis for administrative departments to formulate and adjust radiation protection policies. Methods: According to the radiation health information platform, the data of occupational exposure types of radiation workers in Gansu Province from 2014 to 2023 were obtained. The proportions of occupational exposure types in each physical examination year was statistically analyzed. Results: From 2014 to 2023, the number of medical radiation workers accounted for more than 70% of the total number of radiation workers. The proportion of X-ray imaging diagnostic radiation workers in the total number of medical radiation workers gradually decreased but remained the highest, exceeding 68% annually. The proportion of interventional radiology workers in the total number of medical radiation workers increased from 13.8% to 25.5%. The proportions of radiation therapy and nuclear medicine workers in the total number of medical radiation workers increased slowly. The numbers of interventional radiology and radiotherapy workers in tertiary hospitals both accounted for more than 70% of the total number of such workers in the province. The proportion of interventional radiology workers increased and then decreased. The proportion of radiotherapy workers increased significantly from 70.5% to 93.0%. The number of nuclear medicine workers in tertiary hospitals accounted for more than 80% of such workers in the province. Conclusion: Radiation protection policies and measures should be adjusted according to the changes in the types of occupational exposure. The focus of these policies and measures should differ depending on the level of healthcare institutions, the type of radiological diagnostic and therapeutic services, and the characteristics of various occupational exposure types .

Objective: To establish testing and evaluation methods for radiation shielding performance of a self-shielded radiotherapy system by measuring the radiation levels around the self-shielded head and neck radiotherapy system. Methods: A total of 14 monitoring points were selected outside the restricted zone of the system. Under radiation conditions from five different fixed directions, an ion chamber survey meter was used to measure and identify the maximum ambient dose equivalent rate at the 14 points. The time-averaged dose rate was then calculated based on the workload. In accordance with relevant radiation protection standards, an instantaneous dose rate of 10 μSv/h and a time-averaged dose rate of 2.0 μSv/h were proposed as the criteria for shielding protection evaluation. Results: Based on the ambient dose equivalent rates at the 14 monitoring points outside the restricted zone, the maximum instantaneous dose rate outside the restricted zone was 7.4 μSv/h. With a workload of 15 patients per day, the maximum time-averaged dose rate was 1.0 μSv/h, which can be used as the criteria for shielding protection evaluation. Conclusion: By considering both instantaneous dose rate and time-averaged dose rate, a comprehensive safety assessment of the radiation shielding performance of a self-shielded radiotherapy system can be conducted.

Objective: Developing a new type of full-face respiratory protective mask for nuclear facility sites to enhance the sound transmission function and improve the facial adaptability. Methods: Combined with feedback from on-site practical needs, this study utilized finite element simulation and ergonomic design methods to investigate the voice transmission units of full-face masks and the facial features of workers at key nuclear facilities. Based on the research results, a new full-face respiratory protection mask structure was designed. Results: The optimized structure of passive thin film voice transmission unit significantly enhanced voice transmission efficiency, reducing average voice transmission loss by approximately 70% compared to the control group using thin plate units of equivalent thickness. The existing facial feature test panels insufficiently cover and unevenly classify the facial features of workers at key nuclear facilities. In this study, a specialized test panel based on measurement data achieved a total coverage of 98.5% with high distribution uniformity within each class, providing effective guidance for redesigning full-face mask structural parameters. In comparison to foreign products currently utilized in nuclear facilities, the newly designed full-face mask structure exhibited excellent tightness and structural safety and reliability, and can be cleaned, decontaminated, and reused. Conclusion: The results of this study provide significant guidance for improving and optimizing full-face respiratory protection mask used at nuclear facilities, as well as promoting domestic production of high-quality full-face respiratory protection masks.

Objective: To compare the results of accumulation and continuation methods in indoor radon measurement. Methods: The radon concentrations in 30 households in 7 provincial capital cities of China were simultaneously measured using both accumulation and continuation methods. Results: The radon concentration measured by accumulation method in 30 households ranged from 21 to 323 Bq/m³, with a median M(P₂₅, P₇₅) of 70.5 (43.8, 111). The radon concentration measured by the continuation method ranged from 16.1 to 258 Bq/m³, with a median M(P₂₅, P₇₅) of 100 (51.3, 141). The average relative percent deviation between the two measurement methods was 41.8%. There were significant differences among the measurement results at 8, 16, and 24 h by the continuation method. Pairwise comparisons showed there were statistical diffferences between 8 h and 16 h, as well as between 8 h and 24h; however, no statistical significance was found (P < 0.05), between 16 h and 24 h. Conclusion: The overall continuous measurement results of the 30 households were higher than those of cumulation method. The comparison between accumulation and continuation measurement results did not show a high level of correlation (r=0.49). The continuation method is significantly affected by environmental factors, and the length of the measurement period can affect the measurement results. The selection of indoor radon measurement methods should consider the purpose, sample size, and environmental conditions.

Objective: To study the unqualified items in the reported quality control tests of linear accelerators, analyze the issues in quality control tests, and propose the key points and development directions for accelerator quality control test in China. Methods: A literature review was conducted using the CNKI database to analyze the qualified rates of test items and the issues in quality control tests. Results: In the literature on the quality control tests of linear accelerators, except for a few provinces where the qualified rates of all test items were 100%, unqualified items were reported in most of the literature. There were unqualified items related to X-ray and electron beam in different reports. Error of dose indication was the unqualified item with the highest occurrence rate in X-ray test, and the item with the lowest qualified rates in X-ray and electron beam tests. The lowest qualified rate of X-ray dose indication error was 73.5% in 2016, and the lowest qualified rate of electron beam dose indication error was 46.2% in 2017. Conclusion: Tests should be carried out strictly according to the items and intervals specified by the quality control test standards. Hospitals, radiation health technology service institutions, and health administrative departments should each fulfill their respective responsibilities, work together, and place emphasis on ensuring effective quality control tests of linear accelerators to further enhance the overall quality control standards for these devices.

Objective: To investigate the bone protective effects and underlying mechanisms of 900MHz radiofrequency radiation (RF) at different power densities (50, 150, and 450 μW/cm²) on an ovariectomy-induced osteoporosis mouse model. Methods: Sixty 3-month-old C57BL/6 female mice were randomly divided into Sham group (sham exposure), OVX group (ovariectomy), OVX + LRF group (OVX + 50 μW/cm² RF), OVX + MRF group (OVX + 150 μW/cm² RF), OVX + HRF group (OVX + 450 μW/cm² RF), and OVX + E2 group (OVX + estradiol). Ovariectomized mice in the OVX + RF groups were exposed to RF of varying power densities for 4 hours daily. Ovariectomized mice in the OVX + E2 group received intramuscular injections of estradiol (0.04 mg/kg) every two days. After four weeks of intervention, Micro-CT, ELISA, RT-PCR, and immunohistochemistry were employed to analyze bone density, bone microstructure, serum bone metabolic markers, and the expression of related genes and proteins. Results: Compared with the Sham group, the OVX group showed significantly decreased bone mineral density (BMD) and bone microstructure indicators such as BV, BV/TV, Tb.Th, and Tb.N, significantly increased bone microstructure indicator Tb.Sp, significantly decreased serum estradiol, significantly increased serum CTX-I, TRACP-5b, BGP, and OPG, significantly increased Nfatc1 and Runx2 mRNAs, and significantly increased OPG and RANKL. Compared with the OVX group, the OVX + MRF group and OVX + E2 group exhibited significantly increased BMD, BV, BV/TV, Tb.Th, and Tb.N, significantly decreased Tb.Sp, significantly increased serum OPG, Runx2 mRNA, and OPG, and significantly decreased serum CTX-I, TRACP-5b, Nfatc1 mRNA, and RANKL. Compared with the OVX group, the OVX + LRF group showed significantly increased cortical bone BMD and Tb.Th, the OVX + HRF group showed significantly increased cortical bone BMD and serum CTX-I and TRACP-5b, and the OVX + MRF group showed significantly increased serum BGP. Among the three power densities, the 150 μW/cm² RF showed the most significant effect. Conclusion: The 150 μw/cm² 900 MHz RF can counteract the abnormalities in serum bone metabolism biomarkers, the decrease in BMD, the degeneration of bone microstructure, and the increase in bone resorption caused by ovariectomy in mice.

Objective: To understand the types, proportions, and radiation dose levels of pediatric cardiac interventional procedures. Methods: A retrospective analysis was conducted using the basic information and radiation dose data from all cases of pediatric cardiac interventional procedures performed at two tertiary medical institutions in Beijing from July 2023 to August 2024. The data included air kerma-area product, reference point air kerma, and fluoroscopy time. Descriptive statistical analysis was conducted to evaluate the basic information and dosimetric indicators of the procedures. Non-parametric tests were employed to examine the differences between variables, and Spearman’s correlation coefficient was utilized to investigate the relationships among various factors. All cases were categorized into the diagnostic group and the therapeutic group. In the diagnostic group, the majority of procedures involved catheter examinations and angiography for identifying the type of disease. In the therapeutic group, the primary procedures included patent ductus arteriosus, atrial septal defect, ventricular septal defect, patent foramen ovale, pulmonary stenosis, radiofrequency catheter ablation, major aortopulmonary collateral arteries, complex congenital heart diseases, and other interventional procedures. Results: The survey comprised 1008 cardiac interventional procedures involving 476 males and 532 females. The ages of the participants ranged from 0 to 15 years and the body weights from 4.5 to 105 kg. Among these participants, 92 and 916 were classified in the diagnostic and therapeutic groups, respectively. The proportions of interventional procedures were in the order of atrial septal defect (36.9%), radiofrequency catheter ablation (22.3%), patent ductus arteriosus (15.1%), complex congenital heart disease (4.8%), patent foramen ovale (3.1%), pulmonary stenosis (3.1%), ventricular septal defect (2.2%), other procedures (2.0%), and major aortopulmonary collateral arteries (1.5%). The radiation doses of different interventional procedures were statistically different (P < 0.05), with air kerma-area product ranging from 0.02 to 658.4 Gy·cm², reference point air kerma from 0.1 to 2524 mGy, and fluoroscopy time from 0.2 to 62 min. Conclusion: In pediatric cardiac interventional procedures, there is considerable variability in radiation doses for the same type of procedure. Additionally, radiation doses for identical procedures vary between different medical institutions, and a few cases carry a risk of deterministic effects.

Objective: To study the impact of high radon exposure in non-uranium mines on the occupational health of miners in Jiayuguan, China. Methods: Miners with high radon exposure in non-uranium mines who underwent occupational health examinations at the designated occupational disease specialist hospitals in 2020-2022 were selected as the exposure group (167), and people with no history of radon exposure during the same period were selected as the control group (134). The health examination data of the two groups were collected for statistical analysis. Results: In the exposed group, the rates of ophthalmologic examination abnormality, electrocardiogram abnormality, micronucleus test abnormality, chromosomal aberration, pulmonary nodule detection, liver function abnormality, and leukocyte abnormality were 1.20%, 4.79%, 0%, 0.60%, 37.13%, 43.71%, and 16.77%, respectively. The detection rates of pulmonary nodules and leukocyte abnormalities in the exposed group were significantly higher than those in the control group (P < 0.05). The detection rate of pulmonary nodules increased with working age in the exposed group (P < 0.05). Among different types of work, the detection rates of pulmonary nodules were relatively high in internal combustion overhaul workers, filling workers, and ore carriers (P < 0.05). The rate of liver function abnormalities increased with age (P < 0.05). The rate of leukocyte abnormalities increased with the increase in working age (P < 0.05). Conclusion: Radon exposure has a detrimental effect on the health of non-uranium mine workers, which is mainly manifested by increased detection rates of pulmonary nodules and leukocyte abnormalities. Targeted preventive measures need to be taken to protect the health of miners.

Objective: Based on the radiomics features extracted from the unenhanced CT images of the lower abdomen, a variety of machine learning models were constructed to explore their application value in the assessment of split renal function. Methods: A retrospective analysis was conducted on the unenhanced CT images from 240 single kidneys in patients with clinically suspected renal dysfunction. Based on the results of single-photon emission computed tomography renal dynamic imaging, the cases were classified into the normal glomerular filtration rate group (n=118) and the decreased glomerular filtration rate group (n=122). The region of interest was outlined on the unenhanced CT images and the radiomics features were extracted. The features were selected by correlation analysis and least absolute shrinkage and selection operator, and the machine learning models were constructed based on the algorithms of decision tree, support vector machine, random forest, logistic regression, and extreme gradient boosting. Area under the receiver operating characteristic curve, accuracy, sensitivity, and specificity were calculated to compare the performance of different models. Results: Sixteen radiomics features were selected for constructing the machine learning models. The support vector machine model showed relatively high performance for the assessment of split renal function on the test set, with an area under the receiver operating characteristic curve value of 0.883 (95% confidence interval: 0.804-0.961), an accuracy of 0.778, a sensitivity of 0.811, and a specificity of 0.743. Conclusion: The machine learning models constructed based on unenhanced CT radiomics can be used to preliminarily assess split renal function, which provides an innovative, convenient, and safe method for clinical diagnosis and has positive significance for treatment.

Objective: To investigate the role and related mechanisms of exosomes derived from mesenchymal stem cells (MSCs) in radiation-induced lung injury (RILI). Methods: Human umbilical cord-derived MSCs were isolated and cultured for the extraction and identification of exosomes. Eighteen male SD rats were randomly divided into Control group, RILI group and RILI + exosomes group (EXO group), with 6 rats in each group. Except for Control group, the other groups received a single X-ray dose of 30 Gy to the right lung. Immediately after irradiation, the EXO group was administered 2 × 10⁹ exosomes/kg via tail vein injection. Control group and RILI group were given the same volume of normal saline. Eight weeks post-irradiation, the rats were sacrificed, lung tissue and peripheral venous blood were collected. HE and Masson staining were employed to observe the pathological and fibrotic changes of lung tissue. The levels of serum inflammatory factors IL-6, IFN-γ, TNF-α, and IL-10 were detected by ELISA. RT-qPCR was used to assess the mRNA levels of IL-1β, IL-6, Cdh1, and Col1a1 in lung tissue. The expression levels of Vimentin and TGF-β1 in lung tissue were measured by immunohistochemical staining. The expression levels of AMPK, p-AMPK, and TGF-β1 in lung tissue were detected by Western blot. Results: MSC-derived exosomes were successfully extracted and identified. Compared with RILI group, EXO group showed significantly reduced pathological changes of lung inflammation and collagen deposition. The levels of serum inflammatory factors IL-6, INF-γ, and TNF-α were significantly decreased (P < 0.05), and the level of anti-inflammatory factor IL-10 was significantly increased (P < 0.05). The mRNA levels of IL-1β, IL-6, and Col1a1 in lung tissue were significantly decreased (P < 0.05 or P < 0.01), and the mRNA level of Cdh1 was significantly increased (P < 0.05 or P < 0.01). The levels of Vimentin and TGF-β1 in lung tissue were significantly reduced, while p-AMPK level was significantly up-regulated (P < 0.05). Conclusion: Exosomes derived from MSCs may alleviate RILI by inhibiting inflammatory responses and regulating epithelial-mesenchymal transition mediated by AMPK/TGF-β1 signaling pathway.

Objective: To analyze the status of youth funds and fund management in radiation health research institutes, and to explore the contribution of institutional funds to the cultivation of young scientific and technological talents in the field of radiation health . Methods: The scientific archives of youth funds from 2003 to 2023 were collected for analyses from the aspects of organization and management, application and review, cycle, funding amount, research field, the person in charge of the program, acceptance, and achievements. Statistical analyses were carried out in Excel 2019. Results: The institution-supported Youth Director Funds had a two-year implementation period. A total of 68 funds were granted with a cumulative funding amount of 2.4178 million Chinese yuan. A total of 88 papers were published and 4 patents were granted. Conclusion: The establishment of youth funds has fostered the ability of young scientific and technological talents to independently conduct research and promoted their professional development.

Objective: To assess the retention and excretion fractions for uranium intake via wounds in the organs of adult reference computational phantom, and to improve the evaluation of health risks associated with radioactive isotopes intake via wounds. Methods: A software for evaluation of the internal radiation dose was developed by combining the wound model in International Commission on Radiological Protection Report 156 and the systemic models in the International Commission on Radiological Protection Report 130 and the subsequent Occupational Intakes of Radionuclides series reports. This study was conducted to calculate the uranium retention fractions in adult reference individuals following ingestion through wounds of seven categories of uranium: weakly retained, moderately retained, strongly retained, very strongly retained, colloids, particles, and fragments. We assessed the retention fractions in the wound sites, bones, and liver, as well as the excretion fractions in urine and feces, and compared these results with authoritative results. Results: The retention and excretion fractions of ²³⁸U and ²³⁵U in different forms of intake via wounds showed consistent variations. The retention fractions of weak and moderate uranium in wounds could be ignored after 1 000 d. The retention fractions of strong, avid, and colloid uranium were 10⁻⁴ to 10⁻⁵ after 10 000 d. A significant portion of the uranium present in the forms of particles and fragments exhibited long-term retention in wounds. The bone retention fractions were 1 to 2 orders of magnitude higher than the liver retention fractions. Following the intake of soluble and insoluble uranium, the retention fractions in these two organs decreased and increased, respectively, compared with those observed on the first day. The urinary excretion fractions were approximately 2 orders of magnitude higher than the fecal excretion fractions. Following the intake of soluble and particulate uranium, the excretion fractions decreased. At 1 000 d after the intake of uranium in the form of fragments, the urinary and fecal excretion fractions were 10⁻⁶ and 10⁻⁸, respectively. Conclusion: The calculation results validated the accuracy of the established models, providing data support for the assessment of internal exposure doses in individuals following uranium wound contamination incidents.