Objective To investigate the effect of X-ray on the polarization of mouse microglia BV-2 cells.Methods BV-2 cells at the logarithmic growth stage were randomly divided into the Sham irradiation group and 10 Gy irradiation group. The latter group was given a single X-ray irradiation at a dose of 1.28 Gy/min for 7 min 49 s. The activation rate of BV-2 cells was observed and analyzed under a microscope at 1, 3, 6, 24 h and 48 h after irradiation.The changes of cell morphology were observed by HE staining and immunofluorescence staining; The levels of M1-type activation markers (TNF-α and IL-1β) and M2-type activation marker TGF-β1 in the supernatant of BV-2 cells were detected by ELISA. The levels of polarization-related proteins of M1-type (CD86 and iNOS) and M2-type (CD206) in BV-2 cells were detected by Western blotting.Results Morphological results showed that BV-2 cells became larger, and their protrude became coarse and shorter, showing "amoeba" like changes after 10 Gy X-ray irradiation. Compared with the Sham group, the activation rate of BV-2 cells was significantly increased at 3 h, and reached the peak at 6 h, and began to recover at 48 h after irradiation. ELISA results showed an obvious increase in the level of TNF-α and TGF-β1 48 h after irradiation.The level of IL-1β showed a transient decrease at 3～6 h, increased at 24 h, and reached the peak 48 h after irradiation. Western blotting results showed that CD86 protein level did not change significantly at each time points after irradiation, and iNOS protein level increased significantly at 1, 6, 24 h and 48 h after irradiation. A fluctuating change in CD206 protein level was found after irradiation.Conclusion 10 Gy X-ray irradiation can induce the activation of BV-2 cells in vitro, and the polarization type changes with the time after irradiation.

Objective Based on the monitoring data of the national radiation monitoring network, the natural radiation levels of the country from 2011 to 2015 are analyzed and summarized from the aspects of real-time ambient absorbed dose rate, air, water and soil, etc. Methods Natural radiation monitoring data of air, water, and soil in China from 2011 to 2015 are reviewed, sorted out, classified and summarized. Results From 2011 to 2015, the annual average range of real-time ambient absorbed dose rate is 88～92 nGy/h, and the annual average range of cumulative dose rate is 97～99 nGy/h. The activity concentration of natural radionuclides in air, water and soil is in the daily fluctuation range. Conclusion The real-time ambient absorbed dose rate and cumulative dose rate are in the local natural fluctuation range. The activity concentration of natural radionuclides in aerosol and fallout is at the background level. The activity concentration of natural radionuclides in river water, lake (reservoir) water, sea water and soil is in the daily fluctuation range, and is also at the same level as the national environmental natural radioactivity level survey results from 1983 to 1990.

Objective To study the radiation effects of spent fuel transportation from Guangdong to northwest region under different modes.Methods Using the CRAMTRA 1.0 code, radiation doses of spent fuel transportation under different modes on the typical public and workers were calculated.Results The public collective effective dose per ton of spent fuel delivered to the public had the greatest impact on long-distance road transport (1.65×10^-3 Sv/t), while the Road-Ocean-Rail transport mode had the least radiation impact (2.63×10^-4 man·Sv/t), and the radiation impact of Road-Rail transport mode was the middle (4.51×10^-4 man·Sv/t). The long-distance road transport mode had a significantly higher occupational exposure to workers (6.00×10^-1 man·Sv/t) than that of Road-Rail transport mode (7.93×10^-2 man·Sv/t) or Road-Ocean-Rail transport mode (1.05×10^-1 man·Sv/t).Conclusion The radiation effects of Road-Ocean-Rail transport mode is relatively small.

核能发电具有低能耗,轻污染等优点,但公众普遍对核辐射和核电站建设存有恐惧心理。分析其原因主要是因为核事故本身造成的巨大社会心理冲击,没有及时得到有效的心理干预;核电发展和核事故发生时信息不透明;公众对核与辐射的知识缺乏了解。针对这些原因应加强对核辐射的科普宣教;做到信息公开透明,不隐瞒;从严格选址、提高核电技术、加强安全管理等方面提高核电站的安全性;增强核突发事件应急能力;做好灾后的心理干预,帮助公众及早走出核恐慌。

Objective: To study the effect of cobalt-60 gamma-ray (⁶⁰Co-γ) radiation on the structure of Nialamide, compare the anti-inflammatory activity of irradiation products, and explore the mechanism of action. Methods: After ⁶⁰Co-γ irradiation of nialamide at a dose of 50 kGy, five known compounds were obtained (2-6). The viability of RAW 264.7 (mouse mononuclear macrophage leukemia) cells treated with these compounds was determined by CCK-8 assay. The secretion of interleukin-6 (IL-6), interleukin-10 (IL-10), tumor necrosis factor-α (TNF-α), and prostaglandin E2 (PGE₂) and the content of nitric oxide (NO) were measured using enzyme-linked immunosorbent assay and Griess method. The production of reactive oxygen species (ROS) was detected using DCFH-DA fluorescent probe. The expression levels of cell-induced nitric oxide synthase (iNOS), cyclooxygenase (COX-2), nuclear transcription factor-κB (NF-κB), and IκB were detected using Western blot. Results: The products of nialamide after irradiation did not significantly affect RAW264.7 cell viability (P > 0.05) but showed a strong anti-inflammatory effect (P < 0.01). Compared with nialamide, compounds 2, 3, 4, 6 significantly reduced NO content in LPS-induced RAW 264.7 cells (P < 0.01), and compound 4 had the most significant effect. Moreover, compound 4 significantly reduced the content of IL-6, TNF-α, PGE₂, and ROS (P < 0.05) as well as the expression of iNOS, COX-2, NF-κB, and IκB (P < 0.05) in LPS-induced RAW 264.7 cells. Conclusion: The chemical structure of nialamide is changed after irradiation with ⁶⁰Co-γ, and its product compound 4 shows strong anti-inflammatory activity, which may be related to inhibiting the activation of NF-κB signaling pathway and reducing the release of inflammatory factors. Radiation technology can provide new insights into the changes of molecular structures and physiological properties of natural products.

Objective To observe the mechanism of biological effect induced by low dose γ-rays according to the changes of cell cycle progression of thymocytes and splenocytes in mice. Methods Flow cytometry was used to detect DNA contents of thymocytes and splenocytes after male Kunming mice was irradiated with low dose γ-rays.Results The percentages of G₀/G₁ phase cells was reduced at dose of 50-250 mGy and the percentages of S phase cells increased significantly at dose of 50-100 mGy on thymocytes in irradiated group in comparision with that in sham-irradiated group. The results showed the stimulating effect of thymocytes from G₀/G₁ to S phase induced by low dose γ-rays in mice. The inductive doses of 50-250 mGy resulted in progressive increase of the percentages of (G₂ +M)phase cells in a dose-dependent manner. The arrests of (G₂ +M)phase was induced by 50-250 mGy γ-irradiation. It was found that the percentages of G₀/G₁ phase cells increased after whole-body irradiation with 10-250 mGy and the percentages of S phase cells decreased after whole-body irradiation with 10 mGy、75 mGy and 250 mGy on splenocytes of mice. It suggested that low dose γ-rays produced the arrest of G₀/G₁ phase and the suppressive DNA synthesis of S phase on the splenocytes of mice. Conclusion Low dose γ-rays effectively stimulates DNA synthesis on thymocytes and inhibits it at G₀/G₁ and S phase on splenocytes in mice.

目的 评估MSCT-3D诊断临床肠梗阻价值。方法 按临床手术结果,将114例肠梗阻分为肠道肿瘤、粘连、腹内外疝、套叠、肠切开粪石及蛔虫清除、肠扭转、炎症及缺血和先天肠道畸形共8组。回顾性分析其MSCT表现,评估MSCT-3D对其诊断价值。结果 参比临床肠梗阻手术结果,MSCT诊断87例(76.3%),MSCT-3D确诊103例(90.1%),P<0.05,差异有统计学意义,其中,肠肿瘤、套叠和腹内外疝组,MSCT/MSCT-3D未见漏诊。肠梗阻特异性和非特异性征象明显。结论 MSCT-3D较MSCT获得肠梗阻影像信息显著。

目的 通过对CT拥有量与使用情况的调查,找出CT机配置及使用中存在的问题。方法 相关资料来源于四川省卫生厅汇总和对CT机临床照片的评估结果,以及对各CT机使用情况的问卷调查。结果 四川省CT机区域配置不均,主要集中于经济相对发达地区;CT机临床照片质量欠佳;操作人员技术水平急待提高。结论 优化CT机的区域配置,加快二手机的更新,提高操作人员的业务技术水平以提高CT临床片质量。

Objective By comparing dosimetry characteristics of PTV and organs at risk, time of treatment and cost factors of different radiation field number treatment plans, we research on the most ideal mode for postoperative intensity modulated radiotherapy of rectal cancer (PIMRTRC).Methods The clinical target area of (PIMRTRC) was uniformly defined, and PTV was set as the external expansion boundary of the clinical target volume, which was 5 mm, 4 mm and 3 mm in X, Y and Z, respectively. Using TPS to calculate the dose distribution characteristics of target areas in different irradiation field numbers (5, 7, 9), we compared the irradiated volumes and dose levels of PTVs, bowls, bladders and femur heads respectively. SPSS19.0 statistical software package was used for statistical analysis.Results 5, 7 and 9 radiation field treatment plans can meet the clinical dose requirements. In the three modes of plans, 7 fields and 9 fields were superior to 5 fields in the dose distribution, dose uniformity and conformal degree of the planned target area, but in terms of the treatment time, 5 fields were the shortest and 7 fields were superior to 9 fields. In the protection of small intestine, 7 fields and 9 fields were better than 5 fields; In bladder protection, 9 fields were superior to 7 fields and 5 fields; In terms of femoral head, 5 fields were superior to 7 and 9 fields.Conclusion Based on the comprehensive planning of the dose distribution of PTV, the protection of the normal tissues around the tumor, the treatment time and the treatment cost, it is suggested to select the appropriate radiation field number according to the specific situation and focus of the patients in the clinical work of intensity-modulated radiation therapy for rectal cancer after surgery.

Objective: To investigate the levels and variations of radon concentration in Wuhan subway and to provide data support for ensuring public radiation safety. Methods: The typical sampling method was used to select 18 stations from Wuhan Metro Line 2, Line 3, and Line 7 for the measurement and evaluation of radon in the air. Using RAD7 electronic radon detector and continuous radon measurement method, radon concentrations in station platforms and station halls were investigated. Analysis of variance and t test were used for statistical analysis. Results: The concentration of radon in Wuhan subway ranged from 8.8 to 16.2 Bq/m³, with an average of 11.5 Bq/m³, which is far lower than the limit set by Requirements for Radiological Protection for Radon in Public Underground Structure and Using Geothermal Water (WS/T 668-2019). There was no significant difference in radon concentration between station platform and station hall (t = −0.081, P > 0.05). There was no significant difference in radon concentration between different lines (F = 0.338, P > 0.05). On the whole, the radon concentration in summer was lower than that in winter, and there was no significant difference between months (F = 1.280, P > 0.05). Conclusion: The radon concentrations in Wuhan subway result in low-dose radiation, and there is no significant health risk of radon exposure.

Objective: To analyze the basic situation of medical radiation resource allocation in Hefei, and provide the basis for the health administrative department in the generation of development plans and policies related to radiological diagnosis and treatment resources. Methods: Based on the 2022 Hefei Radiological Health Monitoring Project, the survey used a questionnaire on the basic situation of radiological diagnostic and treatment institutions to investigate the types and quantities of radiological diagnostic and treatment equipment, the number of radiological staff, and the provision of personal protective equipment of radiological diagnostic and treatment institutions at various levels. Results: There were totally 426 radiological diagnosis and treatment institutions, 3345 radiation workers, and 1069 sets of radiological diagnosis and treatment equipment in Hefei. There were 22 (5.16%) tertiary radiological diagnosis and treatment institutions and a total of 2511 (75.07%) radiation workers in these institutions. There were 336 primary and unclassified radiological diagnosis and treatment institutions and a total of only 404 (12.08%) radiation workers in these institutions. For each radiological diagnostic and treatment device, tertiary hospitals were equipped with 6.20 radiological workers, secondary hospitals with 2.06 radiological workers, and primary and unclassified hospitals with 1.23 radiological workers. The number of workers allocated per device was significantly higher in tertiary hospitals than in secondary and primary/unclassified hospitals. The quantity of various types of radiation protection supplies was generally sufficient to meet the needs for conducting radiological diagnostic and treatment procedures. Conclusion: From this survey, it was evident that the city of Hefei had a relatively abundant allocation of radiological diagnostic and treatment resources. However, there were two main characteristics observed in the distribution of medical radiation resources across the city: uneven distribution among medical institutions of different levels and among various districts and counties. Therefore, it was recommended that the government and health administrative departments adjusted the policies regarding the allocation of medical radiation resources and large medical equipment to ensure scientific and rational deployment of radiological diagnostic and treatment equipment.

Objective To track and evaluate the implementation of the Radiation Shielding Requirements in Room of Radiotherapy Installations—Part 1: General Principle (GBZ/T 201.1–2007) among relevant personnel in medical radiation institutions, and to provide a scientific basis for revising the standard. Methods According to the Guidelines for Health Standards Tracking Evaluation (WS/T 536–2017) and the implementation protocol of standard evaluation, an online survey was conducted among 212 relevant workers from 146 medical radiation institutions across 18 provinces in China. The data were aggregated and analyzed with the use of Microsoft Excel 2010. Results A total of 215 questionnaires were returned, of which 212 were valid. Among the valid respondents, 77.8% believe that this standard is universally applied; 96.2% believe that this standard can meet work needs; 63.7% have participated in relevant training on this standard; 74.1% use this standard once or more per year; and 10.8% believe that this standard needs to be revised. Conclusion Medial radiation workers have a high rate of awareness of the basic information and content of the standard, but the understanding and application of the standard content need to be improved. We recommend that relevant departments further strengthen the promotion of and training on the standard, revise some content based on actual situation, and improve workers’ ability to use the standard.

Objective: To investigate air radioactivity contamination, surface contamination, ambient dose equivalent rates, and radiation doses to individuals in the treatment room during ¹⁷⁷Lu-DOTATATE therapy. Methods: A ward for ¹⁷⁷Lu-DOTATATE therapy was selected in the nuclear medicine department of a general hospital. Air and surface radioactivity samples were collected before and after therapy for four patients. Ambient dose equivalent rates were measured around the four patients following the initiation of ¹⁷⁷Lu-DOTATATE therapy. Measurements were taken at distances of 0.1, 0.3, 0.5, and 1−4 m (with 0.5 m intervals) from the right lateral midsection of the patient’s torso. The measurement time points included 5, 15, and 30 min after initiation of administration, as well as 0−4 h (with 1 h intervals), 24 h, and 48 h post-administration. Radiation exposure doses for personnel at different distances from the patients were calculated for each time interval. Results: The results of radioactive aerosol detection for all four patients during and after the administration of ¹⁷⁷Lu-DOTATATE were similar to those before administration. Surface contamination was not detected at the measurement locations except for patient number 2. The ambient dose equivalent rates increased with increasing injection dose during the administration. However, the ambient dose equivalent rates decreased significantly within one hour after administration. At the end of the administration, the average ambient dose equivalent rate at a distance of one meter for the four patients was 42.931 μSv/h. From the start of administration to four hours post-administration, personnel maintaining a distance of one meter from the patient received a total radiation dose of 167.64 μSv. Conclusion: Air radioactivity contamination does not occur during ¹⁷⁷Lu-DOTATATE therapy. However, measures should be taken before the commencement of therapy to address potential surface contamination. Both accompanying persons and healthcare staff receive radiation doses below the stipulated dose constraints throughout the treatment process. Therefore, it is necessary to implement appropriate measures to minimize the radiation exposure of healthcare staff.

Objective To analyze the monitoring results of external exposure dose of interventional radiology staff in a tertiary general hospital in Beijing, China, 2018—2020, and to provide a basis for safe guarding staff health and hospital radiation protection management. Methods A total of 321 interventional radiology staff in a hospital in Beijing were selected to collect information on the types of interventional work, positions, and personal dose monitoring results in 2018—2020. The dose monitoring results were analyzed using SPSS 22.0. Results The effective monitoring rate for the three years was 78.82%, 81.65%, and 96.85%, respectively, showing an increasing trend (χ² _trend = 16.134, P < 0.001). The annual dose equivalent per capita was 0.142, 0.142, and 0.265 mSv, respectively. The annual dose equivalent per capita in 2020 was significantly higher than those in 2018 (H = 24.562, P < 0.001) and 2019 (H = 39.378, P < 0.001). The annual dose equivalent per capita in 2020 was in the order of interventional clinician > interventional nurse > technician (H = 10.699, 6.562, P < 0.01). The annual dose equivalent per capitain 2020 was higher in the cardiology interventional department than in the comprehensive interventional, neuro interventional, and vascular surgery departments (H = 35.530, 37.614, 35.496, P < 0.001). Conclusion The number of interventional radiology staff monitored from 2018 to 2020 increased year by year, so did the effective monitoring rate.The external exposure dose was at low levels, which generally meets the requirements of national occupational exposure limits. Training on radiation protection for interventional radiology staff should be further strengthened to raise awareness of radiation protection.

Objective To obtain the levels of terrestrial γ radiation in the high background radiation area (HBRA) of Yangjiang and its control area of Enping.Methods A total of 112 houses in the HBAR and 147 houses in Enping were selected through multi-stage sampling. The in-room and at-gate γ radiation level swere measured by a survey meter(FH40G+FHZ672E-10). Meanwhile, the levels of outdoor γ radiation of selected villages were also measured.Results The indoor and outdoor γ radiation levels in the HBRA were (0.36±0.06) μSv/h and (0.16±0.06) μSv/h, while the levels in Enping were (0.13±0.05) μSv/h and (0.09±0.03) μSv/h, respectively. The levels of indoor and outdoor γ radiation in the HBRA are about 3 and 2 times of those in Enping, respectively, and the differences were statistically significant. The levels of indoor γ radiation in the HBRA were (0.34±0.05) μSv/h and (0.38±0.05) μSv/h for the new houses and the old houses, respectively. While the values in the control area were (0.18±0.02) μSv/h and (0.09±0.03) μSv/h, respectively. The differences between the new and old houses were both significant in the two areas.Conclusion The level of γ radiation in the HBRA of Yangjiang is much higher than that of control area, but the difference between the two areas is decreasing.

Objective To observe the ultrasound images and pathological features of small benign thyroid nodules (nodule diameter of 10 mm and less) with misdiagnosis of papillary thyroid microcarcinoma and analyze the causes of misdiagnosis, so as to improve the diagnostic level.Methods A total of 29 patients with 31 small benign thyroid nodules were enrolled in the study, and all patients were misdiagnosed by ultrasound examinations in the Department of Ultrasound, Zhangjiagang Hospital of Traditional Chinese Medicine Affiliated to Nanjing University of Traditional Chinese Medicine during the period from December 2014 through August 2016. The preoperative ultrasound data and postoperative pathological results were retrospectively reviewed.Results Among the 31 misdiagnosed, small, benign thyroid nodules, the preoperative ultrasound findings mainly included solid nodules (28 nodules), unclear margin (13 nodules), irregular morphology (10 nodules), extremely low echo (16 nodules), anteroposterior/transverse diameter (A/T) ratio ≥ 1 (12 nodules) and calcification (12 nodules). The postoperative pathological diagnosis mainly included nodular goiter (21 nodules), adenoma complicated by fibrosis (5 nodules), lymphocytic thyroiditis (4 nodules) and subacute granulomatous thyroiditis (1 nodule), and the major pathological characteristics included extensive fibrous tissue hyperplasia with hyalinization (25 nodules), lymphocyte infiltration and eosinophilic change of follicular epithelium (11 nodules), calcification (8 nodules), condensed colloid (4 nodules), inflammatory cells infiltration (2 nodules) and old hemorrhage (1 nodule).Conclusion Small, benign thyroid nodules are easily misdiagnosed as papillary thyroid microcarcinoma at ultrasound examinations, which requires a comprehensive diagnosis based on pathological examinations in combination with other approaches.

This review summarizes the basic situation and characteristics of nuclear technology utilization and radiation safety supervision in Sichuan Province, analyzed the main problems of radiation safety supervision, put forward the corresponding countermeasures and suggestions, and provided reference for improving the radiation safety supervision ability of the whole province.

Objective: To investigate the radioprotection and management of yttrium-90 resin microsphere therapy based on the survey and monitoring of treatment institutions in Guangdong Province, China, and to provide technical reference and basis for the subsequent radiation management of this therapy. Methods: Based on the technical data on yttrium-90 resin microsphere therapy collected from both domestic and international sources, an investigation was conducted on some yttrium-90 resin microsphere treatment institutions in Guangdong Province. Radiation level monitoring was carried out in the radioactive workplaces of three hospitals that had conducted yttrium-90 resin microspheres therapy. Environmental X-γ dose rate meters were used for detecting radiation dose equivalent rates, while α and β surface contamination monitors were used for detecting radioactive surface contamination. Additionally, urine samples from two patients were collected within 24 hours post-operation, and total radioactivity was analyzed using low-background α and β counters. Results: During the yttrium-90 resin microsphere therapy, the radiation dose equivalent rates around the digital subtraction angiography rooms in the three hospitals ranged from 0.15 to 0.26 μSv/h, and the radiation dose equivalent rates around the observation wards ranged from 0.17 to 0.69 μSv/h. The β radioactive surface contamination values in the workplace control zones ranged from ＜0.07 to 18.7 Bq/cm², while the values in the supervised zones were all less than 0.07 Bq/cm². The total β radioactivity in the urine of the two patients within 24 hours post-operation accounted for approximately 0.0010% to 0.0013% of the yttrium-90 infusion dose. Conclusion: The radiation levels at the monitoring sites in the workplaces of the three hospitals are below the national standard limits. The radioprotection and management of yttrium-90 resin microsphere therapy in the three hospitals in Guangdong Province are satisfactory.

Objective To grasp the level of external radiation exposure to interventional and nuclear medicine staff, and to evaluate the protective effect of the radiation workers in order to provide a scientific basis for radiological protection and management.Methods Thermoluminescence dose meter was applied to monitor the occupational exposure to individuals according to GBZ 128-2002 "Specifications of Individual Monitoring for Occupational External Exposure" and GBZ 207-2008 "System Performance Testing Specification for Individual External Dose".Results The external exposure of 324 radiation workers including 287 in interventional radiology and 37 in nuclear medicine were monitored in 2015. The medians of their annual doses monitored under aprons were 0.9、1.14 and 0.86 mSv, and the ones monitored over aprons were 1.96、5.86 and 1.37 mSv in Grade ⅢA, Grade Ⅲ and Grade ⅡA hospitals, respectively. Significant differences (P<0.05) were found among the different grades and classes of hospitals.Conclusion The annual effective dose of 324 radiation workers was all under the standard limit value (20 mSv/a). Significant differences of individual exposure observed in different grades of hospital and types of work suggests that effective protection measures should be taken to reduce the radiation exposure, and the individual monitoring should be strengthened.

Objective Through questionnaire survey, behavioral characteristics and radiation cognition status of patients with diagnosis and treatment in nuclear medicine were analyzed to provide help for reducing unnecessary exposure of the public.Methods A self-made questionnaire was used to investigate the behavior of 245 nuclear medicine patients after radioactive drug injection or taken, including travel, accommodation, dining and other behavioral studies, as well as the knowledge about radiation.Results According to the survey, 57.14% of the patients left the hospital after the examination, 61.14% of patients who left the hospital after examination used public transport. 28.57% of the patients ated in public restaurants. 13.06% knew nothing on attention of radiation protection.Conclusion The radiation exposure to surrounding population from nuclear medicine patients should not be ignored. It is necessary to strengthen the administration of nuclear medicine patients, as well as improve their radiation protection cognition.