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@#Abstract: Objective To retrospectively analyze the individual dose monitoring of radiation workers in Chongqing City from 2016 to 2020, so as to provide scientific reference for occupational health monitoring and radiation protection. Methods Radiation workers who performed individual dose monitoring in Chongqing Center for Disease Control and Prevention from 2016 to 2020 were selected as the research objects, and the monitoring data were collected and analyzed. Results A total of 40 926 individuals were included in this study, with a total of 135 622 person-years. The average annual individual effective dose of radiation workers over the five-year period was 0.56 mSv. NR1 and NR5, the ratio of the number of works receiving annual individual does exceeding 1 and 5 mSv to the to the total monitor workers were 13.019% and 0.335%. The annual effective dose per capita in Chongqing City showed a trend of first decreasing, then increasing and then decreasing again over the study period, with significant differences between different years (F=971.754, P<0.001). Although there were some differences in the variation trend of annual effective dose among different occupational categories, the overall trend was decreasing year by year. The average annual effective dose of nuclear medicine and interventional radiology was relatively high, and the difference was not statistically significant (P>0.05). The average annual effective dose of industrial flaw detection and accelerator operator in industrial application was relatively higher, and the difference was not statistically significant (P>0.05). There were statistically significant differences in the per capita effective doses of different occupational categories of medical application in different years (F=8.892-682.852, P<0.001). Among them, the per capita annual effective doses of five occupational categories of medical application were the highest in 2016, and the per capita annual effective doses of interventional radiology were the highest in 2018 and 2019. Conclusions The per capita annual effective dose of radiation staff in Chongqing has decreased year by year from 2016 to 2020, and remained at a relatively low level that meets national standards. The monitoring results suggest that the radiation staff of nuclear medicine, interventional radiology, industrial non-destructive testing and accelerator operator should give special attention to protect their occupational health and safety.
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The air pollution related health hazards have been a major public health issue for a long time. As an important source of air pollution, diesel exhaust (DE) exposure associates with serious adverse health outcomes. Apart from the exposure in general population, extensive occupational DE exposure populations are reported in many industries, such as transportation, mining, shipping, and construction. Therefore, the studies for internal exposure levels, biomarkers, and toxic mechanisms of DE in occupational population are critical for protecting human from DE-posed health hazards. This special column published some novel findings involving DE exposure (internal & external exposure level), multiple biological effects, toxicity mechanisms, key molecular events, and crucial biomarkers. These studies will provide scientific data for controlling DE associated occupational health hazards, formulating effective DE pollution control strategies, and provide a new scientific perspective and evidence for health risk assessment and prevention.
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In March 2011, a nuclear accident happened and released a large amount of radionuclides into the environment in Fukushima, Japan. This review introduced the latest findings on the relationship between childhood thyroid cancer and radiation exposure after the accident in Fukushima. Many reports suggested that there was no accurate correlation between the incidence of childhood thyroid cancer and the local external dose due to the accident at the Fukushima Daiichi nuclear power, while the relationship between the two varied with method of dose calculation and statistics. Also there was no clear evidence that radiation exposure had a negative impact on children′s thyroid, and the increased incidence of thyroid cancer may be due to over-screening.
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Objective To analyze and compare the data of Yunnan Center for Disease Control and Preventionin national individual dose monitoring ability assessment for external exposure in 2017—2019 and summarize the assessment experience, and to improve monitoring ability and quality. Methods Ability assessment preparation was carried out according to the requirements of The National Comparison Scheme for Individual Dose Monitoring Ability, and blind samples of individual dosimeters were sent. After the blind samples were measured in the laboratory, the results were judged according to the judgment methods in the Testing Criteria of Personnel Dosimetry Performance for External Exposure (GBZ 207—2016) and the requirements of the assessment scheme. Results In 2017, there was a single-group performance of 0.02-0.08 and a comprehensive performance of 0.06, and the results were judged to be qualified. In 2018, there was asingle-group performance of −0.01 to 0.08 and a comprehensive performance of 0.05, and the results were judged to be excellent. In 2019, there was asingle-group performance of −0.13 to −0.04 and a comprehensive performance of 0.08, and the results were judged to be qualified. Conclusion The individual dose monitoring system in our laboratory runs stably, and the monitoring results are accurate and reliable. The quality control measures are effective and feasible.
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ObjectiveThe monitoring of fluoride in drinking water in Qingpu District was conducted to evaluate the external exposure of residents through drinking water， and to provide data support for the continuous improvement of drinking water quality in the area and the health level of residents. MethodsFrom 2016 to 2021， the pipe network water was collected from 42 monitoring points in Qingpu District， every month， and the fluoride concentration in the pipe network water was detected by ion chromatography. ResultsThe fluctuation range of fluoride concentration in drinking water in Qingpu District from 2016 to 2021 was between 0.10 and 0.96 mg·L-1. The fluoride in drinking water did not exceed the standard， which was lower than the lower limit of the WHO recommended range. The median fluoride concentration in drinking water in the Qingcaosha water source area was 0.20 mg·L-1， and the median fluoride concentration in drinking water in the Dianshan lake water source area was 0.44 mg·L-1， and the difference between the two was statistically significant （Z=20.260， P<0.001）. The fluoride concentration in drinking water had a decreasing trend year by year， especially in the water supply area of Dianshan lake water system. The fluoride concentration in drinking water in Qingcaosha water source water supply area decreased relatively gently， from 0.25 mg·L-1 in 2017 to 0.20 mg·L-1 gradually. According to the "Chinese Residents' Dietary Nutrient Reference Intake 2013 Edition"， the requirement of 1.5 mg·d-1 of suitable fluoride intake （AI） for adults. About 50% of the residents in the water supply area of Dianshan lake would consume less than0.75 mg·d-1， fluoride through drinking water， which was lower than 1/2 of the AI value. The fluoride content in the water supply area of Qingcaosha water source was relatively low， and 75% of the residents ingested fluoride through drinking water was lower than 0.37 mg·d-1， which was lower than the 1/4 of the AI value. ConclusionThe concentration of fluoride in drinking water in Qingpu District is lower than the sanitary standard of drinking water in China，and the risk of excessive fluoride exposure is very low. However， the fluoride concentration in drinking water has a decreasing trend year by year， and intervention measures should be used rationally to reduce the health risks caused by insufficient fluoride intake.
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ObjectiveTo determine the individual dose level and changing trend in the occupational external exposure of radiation workers in Shanghai， and provide scientific evidence for health risk assessment for radiation workers. MethodsIn the Occupational Health Management System for Radiation Workers of the National Health Commission-External Exposure Personal Monitoring and Management Subsystem， we retrieved the monitoring data of 38 077 external exposure individual dose of all medical radiation workers in Shanghai from 2015 to 2019. Using clustered sampling method， a total of 11 370 radiation workers in medical institutions （including tertiary， secondary， and primary hospitals） were selected in the study. Statistical analyses were conducted using SPSS 22.0. ResultsThe collective annual effective dose of 11 370 radiation workers was determined to be 4.340 person Sv， including 2.270 man·mSv in diagnostic radiology， 1.112 man·mSv in interventional radiology， and <0.5 man·mSv in other categories. The average annual effective dose was 0.382 mSv， which was 0.482 mSv in nuclear medicine， 0.431 mSv in radiotherapy， and <0.5 mSv in other categories. Moreover， the average annual effective dose of 6 workers （0.05%） was higher than 5 mSv， whereas that of 10 453 workers （92%） were less than 1 mSv； in addition， the annual dose of 911 workers （8.0%） was between 1‒5 mSv. All workers had average annual effctive dose lower than 20 mSv. The annual effective dose differed significantly by years （F=161.1， P<0.01）， by occupational groups （F=13.5， P<0.01）， and by hospital levels （F=264.5， P<0.01）. ConclusionThe average annual effective dose of radiation workers in medical institutions in Shanghai is lower than the national standard limit， suggesting proper and adequate radiation protection system and measures in medical institutions.
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Objective To investigate the reasons why the routine monitoring of personal dose of occupational external exposure of some radiological workers in our province reached the investigation level in 2018, so as to provide technical support for the correct decision making of administrative departments. Methods The registration forms for monitoring and verifying the personal dose of occupational external exposure were issued to radiation workers whose periodic dose reached or exceeded 1.25 mSv/ cycle. Results A total of 102 person-times were sent out in 53 verification forms, and 95 person-times were collected in 47 copies. The recovery rate was 88.68%, and 7 person-times did not feedback the verification forms. There were 15 cases of actual exposure, accounting for 15.79%, including 5 cases of radiological diagnostic staff, who did not close the protective door when operating exposure. Among them, the other 80 cases, accouting for 84.21% didn't receive actual exposure. Conclusion The vast majority of radiological workers who reached the survey level didn't receive actual exposure. 5 person-time radiological diagnostic staff, during the work did not close the protective door, subjected to abnormal radiation. Interventional medicine, nuclear medicine and industrial mobile flaw detection workers are at higher risk of abnormal exposures during their work. The suspicious results of the questionnaires without feedback were all less than the annual dose limit and the requirements of audit management. We will strengthen supervision of radiation health protection, raise the awareness of radiation protection among radiation workers, and improve radiation protection management and protection conditions for radiation workers in interventional medicine, nuclear medicine and industrial mobile flaw detection furtherly.
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Objective A case of abnormal personal doses of external exposure was reported in this paper. According to the investigation of the dose rates of the radiation sources and the workplace, the actualdose was estimated correctly. Methods The radiation level of storage containers at work site was measured by BH3103A portable X and γ radiation dosimeter. The thermoluminescence personal dosimeter was placed in the work site for a month, then it was measured with the RGD3 dosimeter to estimate the dose rateat the work site. The actual personal dose of external exposure was calculated based on the dose rateand the effective working time of the staff in the field. Results The location with highest dose rate was the empty containers which had been filled with raw materials. The second was a container filled with ingredients. The dose rate on the surface of empty container is generally higher than that of full container. The time weighted method was used to calculate the possible dose which was 2.32 mSv for this position. Conclusion The personal dose measured by the personal dosimeter was found to be erroneous, and it should be recorded with the revised dose of 2.32 mSv.
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Objective@#To explore the treatment technique, occurrence and development patterns of such radiation injuries as in a major radiological accident in which a victim suffered mild bone marrow radiation sickness combined grade degree Ⅲ acute radiation induced skin injury, based on his dose estimation, clinical manifestations and disease treatments.@*Methods@#History inquiry in detail, earlier physical dose estimation and biological dose estimation were conducted in conjunction with analyzing the chromosome aberration of peripheral blood lymphocytes. The physical dose was estimated by Monte Carlo method.The systematic laboratory and imaging examination was performed to evaluate the condition. The comprehensive analysis was conducted to determine the diagnosis and treatment plan.@*Results@#At 3d after the exposure, "Ren" felt mild pain and discomfortable on the skin of the right index finger. The body of the right hand index finger was covered with blister at 21 d after exposure.The estimation of biological dose was 0.43 Gy (95%CI: 0.31-0.58 Gy), and the physical dose was estimated to be 36-164 Gy for each part of the right hand finger. The hematopoietic system, immune system and endocrine system were normal. The liver function index value was transiently increased. The liver damage resulted from the use of antibiotic-induced combined with the patient′s past medical history and admission examination result, and the relevant antibiotics were discontinued. The liver function returned to normal after liver protection treatment. At 22 d after irradiation, a right finger incision and decompression surgery were performed. The stem cells were extracted and implanted into the right index finger. After 59 days of hospitalization, there was no obvious discomfort in the body, and the right index finger recovered well, as well as the pain significantly relieved, and the knuckle activity was basically normal.@*Conclusions@#The patient with excessive radiation and grade Ⅲ acute radiation skin injury was successfully treated, and local application of autologous adipose-derived stem cell transplantation achieved good result .
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Objective@#To understand and analyze the individual dose level of occupational external exposure of industrial workers in China from 2009 to 2013, and to provide basic data and scientific basis for radiation protection and radiation protection management.@*Methods@#Since January 2009, the individual dose monitoring data of industrial workers were collected through the "National radiological health information platform-individual dose monitoring system". The methods of Kruskal-Wallis test and the Mann-Whitney test were used for statistical analysis of monitoring results for different occupational categories from 2009 to 2013.@*Results@#From 2009 to 2013, a total of 151, 541 people were monitored for the number of industrial radioactive workers, showing a steady upward trend year by year. The average annual effective doses was 1.179 mSv/a. The average annual effective dose of industrial flaw detection, industrial irradiation, luminescent coatings, radioisotope production, logging, accelerator operation and other applications were 0.808, 1.429, 0.315, 1.074, 0.766, 0.576, and 1.510 mSv/a. There was a statistically significant difference in the average annual effective dose between the seven occupational categories (P<0.05) . The average annual effective doses of other application and industrial irradiation workers in 2013 were significantly higher than other occupational categories (P<0.05) .@*Conclusion@#The average annual effective dose of industrial radiation workers meet the requirements of national standards. The exposure doses of industrial radiation and other application radiation workers are relatively high. The radiation protection workplace protection measures should be further improved and improved, and radiation protection knowledge training should be strengthened to protect their occupational health.
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Objective@#To analyze the personal dose of radiation exposure of radiation workers in some medical institutions in Tianjin, and to provide reference for radiation protection work.@*Methods@#Using cluster sampling method, 8718 radiation workers from some medical institutions (including tertiary, secondary and first-level hospitals) in Tianjin from 2014 to 2018 were selected as the subjects of investigation. Monitoring data were collected, analyzed and evaluated.@*Results@#From 2014 to 2018, a total of 8718 persons were monitored, with 14 persons (0.2%) whose annual effective dose was higher than 5 mSv; 8661 persons (99.3%) whose annual effective dose was lower than 2 mSv; 43 persons (0.5%) whose annual effective dose per capita was the highest in diagnostic radiology, which was 0.22 mSv; the annual effective dose per capita of radiation workers in primary and secondary hospitals was higher than that in tertiary hospitals; and the abnormal rate of individual dose monitoring was 73. Personnel, accounting for 0.8% of the total number of monitored personnel; the annual effective dose changes of the four types of radiation workers monitored from 2014 to 2018 showed a downward trend, and the annual effective dose of the four types of radiation workers in 2014 was the highest.@*Conclusion@#Personal dosage of radiation workers in some medical institutions in Tianjin is at a low level, and attention should be paid to diagnostic radiology workers.
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OBJECTIVE: To investigate the individual external dose level of medical radiation staffs in Guangzhou City.METHODS: The medical radiation staffs of Guangzhou City who conducted individual dose monitoring at Guangdong Province Hospital Center for Occupational Diseases Prevention and Treatment from 2008 to 2014 were selected as study subjects by convenient sampling method.Their individual dosage monitoring data were analyzed.RESULTS: A total of 17 754 person-times were monitored in 7 years.The annual collective effective dose was 10 621.1 person·mSv and the median per capita annual effective dose was 0.21 mSv/a.The per capita annual effective dose in 2008-2012 showed an increasing trend each year( P < 0.05),peaked in 2012,and then decreased in 2013 and 2014( P < 0.05).The per capita annual effective dose of radiology staffs in level Ⅱ medical institutions was higher than that of level Ⅲ medical institutions,level Ⅰ medical institutions and those below level Ⅰ( P < 0.01).The per capita annual effective dose of radiation staffs in level Ⅲ medical institutions was higher than level Ⅰ medical institutions and those below level Ⅰ( P <0.01).The effective monitoring rates of radiation staffs monitored for 4 cycles every year increased with time from 2008 to 2014( P < 0.01).The effective monitoring rate increased with the hospital level( P < 0.01).The per capita annual effective dose of the staffs in radiological diagnosis department was lower than that of clinical nuclear medicine,radiotherapy and interventional radiology( P < 0.01).CONCLUSION: The radiation dose of medical radiation staffs in Guangzhou City was within the national standard limit.Protection should be focused on the the staffs in secondary hospitals,clinical nuclear medicine,radiotherapy and interventional radiology.
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Objective@#To determine the personal dose level of radiation workers in medical institutions at the municipal level and below in a city, and to provide a scientific support for strengthening the radiation protection in the city’s medical institutions.@*Methods@#Information of the successful applicants for the "Radiation Worker Permit" from 174 medical institutions at the municipal level and below was collected from October 1, 2011 to December 31, 2014. The annual effective dose was calculated based on the personal dose monitoring report, and indicators including sex, permit application time, hospital level, type of occupational radiation, length of radiation work, blood test, and micronucleated lymphocyte rate were analyzed.@*Results@#Of the 1 143 radiation worker permit applications submitted by medical institutions the municipal level and below in this city from 2011 to 2014, 1 123 provided at least one personal dose monitoring report. The annual effective dose of the radiation workers was 0-4.76 mSv (mean 0.31±0.40 mSv) , and the collective annual effective dose was 351.96 mSv. The annual effective dose was significantly different between radiation workers with different times of permit application, hospital levels, and types of occupational radiation (P<0.05) . Interventional radiology workers had the highest annual effective dose (0.63 mSv) , and annual effective dose was significantly different between interventional radiology workers with different lengths of radiation work (H=10.812, P<0.05) .@*Conclusion@#The personal radiation dose of radiation workers in medical institutions at the municipal level and below in this city is maintained at a relatively low level, suggesting that the occupational environment is relatively safe for these workers. However, more focus should be placed on clinical interventional radiology workers.
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Objective To evaluate the reliability of HARSHAW-3500 thermoluminescence dosimetry system by testing its performances.Methods HARSHAW-3500 thermoluminescence dosimetry system had its performances tested and evaluated according to Verification regulation of thermoluminescence dosimetry systems used in persontal and environmental monitoring forXandgammaradiation(JJG 593-2006),Testingcriteriaofpersonneldosimetryperformanceforexternalexposure (GBZ 207-2016),Specifications for individual monitoring of occupational external exposure (GBZ 128-2016) and Thermoluminescence dosimetry systems for personal and environmental monitoring (GB/T 10264-2014),such as batch homogeneity,repeatability,linearity,incidence angle response,stability,energy response and scale factor,quantity inspection,residual dose,detection limit and etc.Results Testing results of various performance indicators proved to be within the limits according to national and industrial standards.Conclusion HARSHAW-3500 thermoluminescence dosimetry system conforms to the requirements for radiation dose measurement.It is beneficial to the improvement of quality and performance of thermoluminescence dosimetry by performances analysis and evaluation.
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Objective To evaluate the reliability of HARSHAW-3500 thermoluminescence dosimetry system by testing its performances.Methods HARSHAW-3500 thermoluminescence dosimetry system had its performances tested and evaluated according to Verification regulation of thermoluminescence dosimetry systems used in persontal and environmental monitoring forXandgammaradiation(JJG 593-2006),Testingcriteriaofpersonneldosimetryperformanceforexternalexposure (GBZ 207-2016),Specifications for individual monitoring of occupational external exposure (GBZ 128-2016) and Thermoluminescence dosimetry systems for personal and environmental monitoring (GB/T 10264-2014),such as batch homogeneity,repeatability,linearity,incidence angle response,stability,energy response and scale factor,quantity inspection,residual dose,detection limit and etc.Results Testing results of various performance indicators proved to be within the limits according to national and industrial standards.Conclusion HARSHAW-3500 thermoluminescence dosimetry system conforms to the requirements for radiation dose measurement.It is beneficial to the improvement of quality and performance of thermoluminescence dosimetry by performances analysis and evaluation.
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Objective To establish an accurate method for estimating the indoor gamma dose rate from decorative stones.Methods Combining a room model with decorating conditions,the gamma dose rates and dose rate conversion factors (DCF) at 1 m above the floor in the room center were calculated with the Monte Carlo simulations,and the calculation results were verified through experiments.Based on the results,the limit of radionuclide contents in stone materials was further discussed.Results The DCF increases with the increase of area or thickness of decorative stones in the same room.The increase of DCF with the thickness of decorative stone is approximately linear.The DCF also increases with the area of decorative stones,but the increasing trend slows down.For the same decorative stones,the smaller the room,the larger the increase of gamma dose rate.Experimental results were consistent with the simulation results within ± 20％.Conclusions The increase of indoor gamma dose rate depends not only on the radionuclide contents,but also on the area and thickness of the decorative stones as well as the room size.The method used in this study can be used to estimate,more accurately than ever,the additional external exposure to residents due to decorative stones,and it provides a theoretical basis for revising the limit standard on radionuclide contents in decorative materials.
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Objective To describe a simplified generic procedure to evaluate the external exposure dose evaluation in radiological emergency, and to compile the corresponding computer software. Methods Based on the related reports of IAEA, this generic procedure of external exposure dose evaluation in radiological emergency was compiled to computer software by Visual Basic 6.0. Results The generic procedure for evaluation of external exposure dose could be used in the external exposure radiation accident emergency. The actual accident data were input in this software, then the results from this software agreed with those of the actual accident well. The maximum error was 40% , and the minimum error was 6%.Conclusions The generic procedure for evaluation of external exposure dose could provide practical emergency response guidance. The software might help to evaluate the accidental dose more quickly and accurately, and provide scientific basis to take the immediate response actions.
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Purpose To develop a national registry and reporting system of individual monitoring for workers occupationally exposed to ionizing radiation.Methods In accordance with the relevant law,regulations,standards and the current health supervision practice for radiation workers in China,to ensure more effective collection of information on individual monitoring from all levels of service providers across the country and an easy query and analysis of the collected information for both service providers and administrative institutions,the register consisted of an offline-system and a web-based information system.The off-line system consisted of 8 tables,which could easily make annual and period monitoring reports,and upload individual monitoring data in compressed and encrypted format.Web-based system consisted of 6 modules,could easily make S customized tabulations of monitoring data and show 2 trend figures.SSLVPN secure remote access was used in the system.Arranged by the Ministry of Health,training courses provided to all individual monitoring service providers and provincial administrative institutions.Results A new and individual-based national register and reporting system of individual monitoring for workers occupationally exposed to ionizing radiation was successfully developed,and would be officially run soon.Conclusions The establishment and running of the register would be great improvement on the national radiological health reports and produce a far-reaching impact on the individual monitoring in China.