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  • 28 October 2019 Volume 28 Issue 5
      

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  • LIU Libo, CHEN Qiang
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    Radiational thyroid disease is referred to the primary or secondary thyroid function and/or organic changes caused by internal and/or external irradiation of ionizing radiation on the thyroid and/or other tissues of the body. These include acute radiation thyroiditis, chronic radiation thyroiditis, radiation hypothyroidism, radiation benign thyroid nodules and radiation thyroid cancer. Radiation thyroid diseases mainly occur in accidental irradiation, medical irradiation and occupational irradiation. In order to understand the radiational thyroid disease and its correct diagnosis and treatment, we analyzed the pathogenesis, clinical manifestations, accessory examination, diagnosis, differential diagnosis, treatment and prognosis of radiational thyroid diseases.
  • LIU Libo, PIAO Chunji
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    The gonadal diseases caused by ionizing radiation are called radiational gonad disease which include radiation infertility and radiation amenorrhea. Radiation induced gonad disease mainly occure in accidental exposure, occupational exposure and medical exposure. In order to better understand radiation induced gonad disease and correct diagnosis and treatment in this paper, we analyzed the pathogenesis, clinical manifestations, laboratory examination, diagnosis, differential diagnosis, treatment and prognosis of radiation induced gonad disease.
  • LI Jieqing, MAO Xuesong, MA Ya, FANG Lianying, ZHU Wei, HOU Dianjun, JIA Ximing, QIAO Jianwei, LI Weiguo
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    Objective To investigate the lens opacity of interventional radiation workers. Methods The lens opacity of 226 interventional radiologists and 336 diagnostic radiologists was analyzed and evaluated. Results The rate of lens opacity of interventional radiologists was 8.85%, higher than that of diagnostic radiologists (P<0.05).There was no statistically significant difference in lens opacity among interventional radiologists of different gender groups(P>0.05). There were statistically significant differences in the lens opacity rates between the 50+group and other age groups(P<0.05). There were statistically significant differences in lens opacity rates among interventional radiologists of different working age groups (P<0.05). Conclusion Exposure to long-term low- dose radiation can cause the increasing risk of the lens opacity in interventional radiologists. It is necessary to strengthen protection among interventionalradiologists.
  • LI Jie, HAN Lin, WANG Ping, TIAN Chongbin, LV Yumin
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    Objective To explore the relationship between individual exposure dose and micro-nucleus of peripheral blood lymphocytes and provide basis for radiation protection of radiation workers. Method 921 radiation workers were included in this study and were divided into five groups according the type of work[including radiodiagnosis(n=481), radiotherapy(n=153),nuclear medicine(n=83), interventional radiology(n=90)and Industrial flaw detection(n=114).]And micro-nucleus test was used by whole blood of tiny culture method. Results According to the statistical analysis, there was significant difference in the annual average effective dose among the five groups(F=33.809,P<0.05),and it was significant higher in nuclear medicine group and interventional radiology group than that in radiodiagnosis group,radiotherapy group and Industrial flaw detection group(P<0.05);Meanwhile,the micronucleus rate of the interventional radiology group was significantly higher than that of radiodiagnosis group and radiotherapy group(P<0.05).But there was no significant dose-effect relationship between micronucleus rate and individual annual effective dose (P>0.05).Comparison of microuncleus rates among different physical examination categories showed statistically significant differences between pre-job and on-job groups(χ2=168.526,P<0.05).With the increase of age,the micronucleus rate in on-job group tended to rise roughly(P<0.05). Conclusion The genetic damage induced by low dose ionizing radiation still exists in radiation workers. Effective protective measures of interventional and nuclear medical workers should be strengthened to reduce radiation damage.
  • ZHANG Yao, SHAO Xianzhang, LIN Liang, WANG Chengguo, JI Yanqin
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    Objective To investigate the radiation awareness of occupational staff in a typical rare earth ore. Method A questionnaire for the radiation awareness was designed through field observation, literature query and consulting professionals. And the survey was conducted among the occupational staff via the random cluster sampling method. Results The overall level of radiation awareness among occupational staff was generally poor. The cognitive scores of ionizing radiation, internal and external exposure and their main types were higher in the lower dust group than those in the higher dust group (P<0.05), and the cognitive scores on radiation hazard in the lower dust group were also slightly higher than those of the higher dust group (0.05 < P < 0.1). However, there were no statistically significant of age, education level, the pathways of obtaining the radiation-related knowledge, and the knowledge of preventive measures for internal and external radiation between the two groups. Conclusion The overall radiation awareness of occupational staff in the typical rare earth ores should be enhanced, especially for the staff working in the high dust and aerosol concentration environment. The protection awareness was insufficient and radiation training should be strengthened.
  • TAN Li, ZHOU Ning, XIE Xinghua, WU Zhenyu, WANG Zhe, CHEN Yishui, ZHU Ruokai
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    Objective To analyze and evaluate the problems existing in the plane layout of radiation protection control effect evaluation stage of a hospital PET/CT center construction project, and to propose the importance of occupational hazard radiation protection evaluation, especially the pre-evaluation. Method The layout of the PET/CT workplace was analyzed and evaluated on the basis of on-site verification and in accordance with relevant laws, regulations and standards. Results The layout of the PET/CT center was unreasonable, including:the site layout was not arranged from the low activity area to the high activity area, the sanitary passage was not set, the dedicated channel for transport of radioactive drugs and waste was not set. Conclusion The reasonable layout of nuclear medicine workplace is the premise to ensure the optimization of radiation protection, and the pre-evaluation of occupational hazard radiation protection is the key to determine whether the layout is reasonable or not.
  • HUO Haiwei, ZHANG Bingjie, MAO Yuxuan, WANG Xuan, WANG Yan, NIE Jing, LIU Tongzhen, JIA Tianhe, WANG Jianwei, DING Weimin
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    Objective To analyze the quality control test results of the CT machines in Xinxiang City in 2016, so as to promote the development of radiological health work in the city. Methods The CT machines of the entrusted unit in Xinxiang city were tested for quality control according to GB 17589-2011. Results The qualified rate of all ten testing indexes of the CT machine was 85.5%. Conclusion On the whole,the quality control testing results of the CT machine in Xinxiang City are generally satisfying, but there are certain problems in the quality control status of the second-hand CT machine. The maintenance and update of the second-hand CT machine should be further strengthened, so as to protect the safety and health of the examinee and patient.
  • JIANG Lihong, MENG Yuejie, ZHOU Jing, CHEN Yan, WANG Youcheng, SHI Zhenxiang, MA Chao
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    Objective To know the evaluation situation and existing problem of occupational disease hazard radiation protection evaluation of nuclear medical treatment project in Hebei province, and put forward some feasible suggestions. Method To collect relevant information and official reports on the occupational hazard radiation protection evaluation in 32 nuclear medical construction projects commissioned from 2011 to 2018, mainly from the general situation of project, site selection and surrounding situation, layout process and radioactive waste management, and put forward feasible opinions and suggestions. Results Among the 32 nuclear medicine construction projects, 23 were pre-evaluated and 9 were evaluated for the control effect. Nuclear medicine construction projects are mainly concentrated on tertiary hospitals, with 13 (72.33%), followed by 3 private hospitals (16.67%). Five (15.6%) of the projects were not properly located. It is suggested that project units should strengthen shielding protection and strengthen the management of radioactive waste and patients after drug administration. In the layout flow chart of the initial submission, it was found that there were 79 problems such as the intersection of medical, patient and nuclide routes, the lack of functional rooms, and the confusion in the division of the three zones. After the radiation protection evaluation, the number of related problems was reduced to 18. Among them, the division of the three zones and the intersection of internal routes have been resolved. Some problems in the management of gaseous radioactive waste in the initial data of the project have been well solved after radiation protection evaluation. Conclusion Radiation protection assessment of occupational disease hazards in construction projects is an important measure for nuclear medical construction projects to control radioactive pollution and protect personnel and environment safety at the source, which needs to be paid great attention by the construction units and relevant administrative departments.
  • WEI Chao, DU Peng, ZAHNG Wenyi, GAO Jie, WU Quan
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    Objective To investigate the influence of incident screen size on the representative and maximum value of air kerma rate of perspective body surface, air kerma rate of image receptor front screen, spatial resolution and low contrast resolution, by testing 9 philips Allura Xper FD 20 digital subtraction angiography systems. Methods We tested the indexes of the nine radiography unit with the Specification for testing of quality control in medical X-ray diagnostic Equipment (WS 76-2017). The data were collected under auto exposure in perspective mode with the bed 100 cm far away from the ground, and image receiver 30 cm far away from the bed surface, moreover phantom and surveying instrument located at the center of radiation field. All data were analysed by SPSS 23.0. Data were done by Tamhane'T2 test and Kruskal-Wallis test. Pearson correlation analysis was used for correlation analysis. The difference was statistically significant by P<0.05. Results The experimental results of the nine units showed that, reducing the field of view of digital subtraction angiography could significantly improve spatial resolution and low contrast resolution, and increase the representative value of air kerma rate of perspective body surface and air kerma rate of image receptor front screen, but had no effect on the maximum value of air kerma rate of perspective body surface. Conclusion In this study, we found that changing the field of view of digital subtraction angiography could cause the influence of incident screen size on the representative value of air kerma rate of perspective body surface, air kerma rate of image receptor front screen, spatial resolution and low contrast resolution. And that result was closely related to the changes of kV and mA caused by FOV of digital subtraction angiography.
  • QU Yantao, QUAN Hongtao, HAN Yongchao
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    Objective By analyzing the waveform of the output signal of Si-Sonic Microphone and the variation of JFET DC parameters under γ-ray irradiation conditions, the radiation damage effect of the sensor is obtained and methods to improve the radiation resistance are proposed. Methods From the perspective of the ionizing radiation damage effect caused by γ-rays, the Si-Sonic Microphone and the JFET irradiation experiments under 60Co γ-ray were designed. Results Output signal of Microphone increases rapidly with a linear distortion generated at the positive parts of the amplitude after several minute of irradiation; output signal reduces significantly after one hour irradiation; the single amplitude continuously decreases with the cell voltage reduction. The source drain current and transconductance of N channel JFET decline slightly and no significant change of P channel JFET DC parameters is shown after 432 kGy irradiation. Conclusion JFET has good irradiation resistance, and P channel JFET is better than N channel JFET. The irradiance effect of γ-ray on Si-Sonic Microphone is mainly reflected in the radiation damage of ionizing radiation to its integrated N channel MOS devices. Three methods for enhancing the γ-ray irradiation resistance of the Si-Sonic Microphone are proposed by the experimental data.
  • KONG Yuxia, CUI Limeng, WANG Huan, MENG Qinghua, MA Yongzhong
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    Objective To understand the correlation between gross alpha and beta radioactivity concentration in atmospheric aerosols and haze in Beijing from 2016 to 2017. Methods Large-flow aerosol sampling in Beijing was carried out, and radioactivity aerosol samples were measured by a BH1217 low background alpha-beta measuring instrument. Results Radioactive concentrations of gross alpha and beta in 32 monitoring days in 2016 were 0.36~9.02 mBq/m3 and 0.06~3.75 mBq/m3 respectively. The ranges of gross alpha and beta radioactivity concentration of atmospheric aerosols in 47 monitoring days in 2017 were 0.01~4.31 mBq/m3 and 0.02~2.61 mBq/m3 respectively. Conclusion Gross alpha and beta radioactivity concentrations in the atmosphere are seasonally related, however there is no significant correlation between them and PM2.5 or PM10 concentrations.
  • OU Pin, LI Yucheng, YOU Huiyuan, HUANG Lifang, ZHENG Xueting, CHENG Baogen, YU Qingqing, CAO Hongbao, CHENG Jinpeng, TAN Minyu
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    Objective To master radioactive pollution level of drinking-water in Huizhou caused by operation of Daya Bay Nuclear Power Base within a radius of 30 km of the base. Methods Radioactive levels of gross α,gross β and 40Kβ for source water,processed water and terminal water from seven main tap water supplies were determined to decide whether radioactive pollution on drinking-water is caused by Daya Bay Nuclear Power Base and whether radioactive indexes of drinking-water are in accordance with requirements of water quality,compared to radioactive level of background investigation and screening. Results In high flow period,radioactive levels of gross α,gross β and 40Kβ for source water were(0.009±0.003~0.255±0.029),(0.025±0.003~0.211±0.009)and(0.021~0.111)Bq/L,respectively; radioactive levels of gross α,gross β and 40Kβ for processed water were (0.011±0.004~0.021±0.003),(0.039±0.003~0.143±0.007)and(0.025~0.108)Bq/L,respectively; radioactive levels of gross α,gross β and 40Kβ for terminal water were (0.007±0.003~0.027±0.003),(0.054±0.002~0.123±0.006)and(0.037~0.109)Bq/L,respectively. In low flow period, radioactive levels of gross α,gross β and 40Kβ for source water were(0.011±0.003~0.100±0.008),(0.050±0.003~0.139±0.004) and (0.022~0.069)Bq/L,respectively; radioactive levels of gross α,gross β and 40Kβ for processed water were (0.005±0.002~0.118±0.009),(0.045±0.003~0.119±0.004)and(0.022~0.065)Bq/L,respectively; radioactive levels of gross α,gross β and 40Kβ for terminal water were (0.010±0.003~0.090±0.009),(0.043±0.002~0.112±0.005)and(0.024~0.068)Bq/L,respectively. Conclusion During its operation,the base does not cause obviously radioactive pollution to the drinking-water in Huizhou within a radius of 30 km of the base,and radioactive level of the drinking-water meets the requirements of drinking-water quality.
  • WANG Lihua, SHENG Leyuan, TAO Shenghui, SUN Yuyu
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    Objective Discussion on accuracy of counting 14C as CaCO3 by suspension method. Methods The lower level background samples,the optimum scintillation solution、the appropriate standard sample and the best spectral analysis width were found by measuring two kinds background samples,four Standard samples in two kinds scintillation solutions. Then one examining sample and two comparison samples were measured by conclusions. Results Self- made CaCO3 power,Methylbenzene-Triton X-100 scintillation solution,the best spectral analysis width(67-369)and the appropriate standard samples were used to measure the examining sample and the comparison samples. The results are all acceptable,the relative deviation is 4.7%,11.7% and 0.2% respectively. Conclusion The background level,the scintillation solution and the standard samples are the key influencing factors,should be selected carefully.
  • ZHAO Xinjing, DING Hongshen, LIU Wenna
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    Objective To establish an analysis and measurement method for tritium in environmental organisms samples and to verify the applicability of the method by experiments, to provide technical support for the formulation of analytical criteria for tritium in environmental organisms. Methods Tissue free water tritium samples and dry organisms samples were prepared by vacuum freezing separation of fresh organisms samples, organically bound tritium samples were prepared by reaction of dry organisms samples with oxygen,and tritium radioactivity was measured with a low background liquid scintillation counter. Results The relative standard deviations of tissue free water tritium and organically bound tritium were 8.50% and 16.3% respectively. The recovery rate of tissue free water tritium via addition of reference materials was 96.7%, and the relative error of organically bound tritium in a given radioactivity sample was -2.38%. The low limit of detection of tissue free water tritium and organically bound tritium were 1.07 Bq/kg·fresh and 0.0539 Bq/kg·fresh respectively. Conclusion This method can be used for the analysis and measurement of tritium in environmental organisms samples.
  • XIA Zhongliang, NIE Peng, ZHOU Yidong, PENG Shunmi
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    Objective To calculate the Wigner energy of the graphite reflector of heavy water research reactor (HWRR), and provide technical support for the decommissioning of HWRR. Methods Based on the position, direction cosine and energy information of neutrons acquired from the PTRAC card of MCNP, the energy distribution of primary knock-on atoms (PKA) can be obtained. After data filtering, an input file is generated from MATLAB for SRIM code to simulate the cascading damage process of PKA in graphite. Considering the effect of temperature on the irradiation damage, the distribution of Wigner energy accumulation in the graphite reflector is obtained. Results The result shows that the Wigner energy in the graphite reflector of the heavy water research reactor (HWRR) is concentrated on the inner layer close to the core, and located in the upper region of reflector with a maximum value of 1 215.4 J/g. Conclusion The basic agreement between the results from Hanford experiment and our calculation indicates that the simulation method established in this study is workable for calculating the accumulated Wigner energy in graphite of reactor reflector.
  • HE Xianwen, HUANG Yilin, PENG Chong, CHEN Baocai, ZHOU Hualong, LIU Manqing, XIAO Yuanwen, FENG Liangliang
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    Objective To investigate the gross α and β activity concentrations in drinking water sources of Nanning, and accumulate the environmental background to ensure drinking water safety and public health. Methods The activity concentrations of gross α and β were measured using the low background α/β counter (LB4200), and the results were used for dose estimation. Results The mean concentrations of gross α and β were 0.017Bq/L (<0.008~0.038 Bq/L) and 0.061Bq/L (0.012~0.130 Bq/L), respectively. Both of them were below the national limits set by GB 5749-2006. The annual effective doses were estimated to be 2.09~9.93 μSv and 0.044~0.476 μSv for the gross α and β activities respectively, and they were also below the WHO recommended reference level for all water samples. Conclusion The radioactivity level in drinking water sources of Nanning is within the normal background range and will not pose a threat to the public health.
  • DIAO Lei, ZHAO Yuhang
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    Objective To reach the goal of the safe shutdown of a certain nuclear facility by scientific and reasonable andr radiation protection measurements. Methods Before carrying out the safe shutdown work, the radioactive source term was investigated, radiation risk during the implement was analyzed according to the investigation result, the process of safe shutdown was designed, and proper radiation protection plan was formalized and implemented. Results According to the radiation survey of this facility, it was revealed that the major contaminated nuclides were 137Cs, 90Sr and 241Am. The radioactive contamination area was relatively large and the contamination degree was severe. Besides, the gamma radiation and radioactive aerosol were relatively high in working area. The radiation risk of this program was analyzed according to the survey result. Proper work process was followed and good radiation protection was undertaken to ensure the radiation safety of this work. Conclusion The radiation protection work met the demand of this program, and provided reference for scientific researchers and management departments engaged in nuclear facility decommission work.
  • LIU Ke, HU Han, HOU Zhanxian, GONG Hongyue, XU Han, ZHOU Yuhang
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    Objective To compare the time constants of two 451P ionization chamber dosimeters, and to discuss the application of the time response modified formula. Methods In the condition of two exposure level of X-ray machines, and different measurement modes were used to measure and record the ambient dose equivalent rate for the higher dose ratelevels. The time constants (τ) of the instrument were conducted by fitting the data using the time response of having a capacitance C and a resistance R in series. Results The fitting time constants (τ) of two 451P ionization chamber dosimeters were (3 476.4±124.9) ms, (3 676.4±144.4) ms for the range of 0 μSv/h to 5 μSv/h, (2 051.6±249.5) ms, (2 047.0±271.9) ms for the automatic range of 0 μSv/h to 50 μSv/h, and (1 123.8±85.9) ms, (1 242.0±91.8) ms for the fixed range of 0 μSv/h to 50 μSv/h, respectively. Conclusion No significant statistical difference was found in the time constants of two 451P ionization chamber dosimeters, but all of the fitting time constants were statistically significant different to the parameters in the operators manual. So the exposure time and measurement mode should be appropriately chosen for protection detection, and the results should be corrected by the time response correction formula with the certificated time constant.
  • ZHANG Lei, YANG Kai, WANG Xinggong, WANG Qiang
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    Objective To investigate the differences in the background radiation values of different departments in medical institutions in personal dose monitoring. Methods According to different occupational categories, place the following background dosimeters for each department and the administration office ina top three military hospital, compare and analysis the differences of the measured background radiation values between them. Results The background radiation values of the monitored unit were in the range of 0.22~0.33 mSv. The measured values of dosimeters which were placed in the bookcase, desk drawer and on the desk surface of the administration office were 0.28±0.02 mSv, 0.28±0.01 mSv and 0.31±0.01 mSv respectively.Compared with the administration office, the background radiation values of radiology department, dental department, radiotherapy center, and catheter room were larger respectively,in which exists statistical significance (P<0.05), while the background radiation values of CT area, PET-CT control room, neurosurgery, laboratory were smaller respectively,in which also exists statistical significance (P<0.05),but there was no statistical difference between the values of the department of cardiology and the administration office (P>0.05). Conclusion Single background radiation value cannot be used to represent the background radiation value of a occupational categoryand a unit. Placing the following background dosimeters for each department can reduce the error of the background radiation value and enhance the ability of quality control.
  • CHEN Wei, YU Guobing, CHEN Zhi, GU Xianbao, WEN Deyun, DU Qin, HE Xu, WANG Jinlong
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    Objective To investigate and study the radioactivity levels in the process of mining and utilization of stone coals in southern Anhui, and evaluate its impact on the surrounding environment and residents' dose. Methods By taking the stone coal mine, stone coal derivative products and surrounding environment in the typical stone coal mine area of southern Anhui as the research object, the relevant data were monitored on-site or through laboratory analysis. Results The highest contents of 238U, 226Ra and 210Pb in stone coal mines were up to 1 298 Bq/kg, 1 598 Bq/kg and 1 212 Bq/kg, respectively. It belongs to the category of associated radioactive minerals. Having been burned, the concentration of 210Pb in the coal slag was generally reduced. The contents of some natural radionuclides in the soil and water samples around the mining area were much higher than the average level of the surveyed area. The annual effective dose per capita of external radiation in the stone coal carbide brick building was estimated to be 1.01~1.24 mSv, and the annual effective dose due to inhalation of 222Rn and its progeny was 1.8~4.9 mSv. Conclusion The natural radionuclides in the stone coal have been partially transferred to the surrounding soil and water. The annual additional effective dose of residents living or working in carbonized brick houses has significantly increased.
  • WU Lan, LI Xin
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    Objective To provide scientific basis for nuclear and radiation safety regulation and radiation environmental protection work to ensure public health and radiation environmental safety. Methods On-site monitoring the absorbed dose rate in air from terrestrial gamma radiation, and laboratory analysis of radioactivity in surface water, soil and biological samples in the area of Inner Mongolia Autonomous Region from 2016 to 2018. Results Both the level of terrestrial gamma radiation and the radioactivity in surface water and soil samples were within the range of the survey values in the Inner Mongolia Autonomous Region from 1983 to 1990. Conclusion From 2016 to 2018, the radiation environmental quality of the Inner Mongolia Autonomous Region was generally good, within the range of background fluctuations. It is recommended to gradually increase the number of radiation environmental quality monitoring points to the county level, and to strengthen personnel, equipment, and professional technical training of radiation environmental monitoring institutions at all levels.
  • JIN Hui, ZHANG Hui, ZHANG Zhucun, CHEN Xiaojie, SHAO Yanjie, XU Rong, JIANG Fajin, HAN Zhengwei, LIU Xuefeng, KONG Lingyan
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    Objective To improve the management of dangerous radioactive sources and ensure their radiation safety. Methods The safety status of radioative sources of Class III and above, the data of environmental radiation and individuals dose, and the problems and management experiences found by on-site supervision and inspection were summarized and analyzed. Results In 2018, there were 336 radioactive sources ofClass III and above in Yunnan Province, and they were mainly used in the fields of industrial irradiation and radiation therapy. The radiation facilities were basically intact, and the gamma radiation levels around the source sites were between 0.045~0.204 μGy·h-1. The individual dose met the limit requirement of occupational personnel. However, there still existed some deficiencies in the maintenance of security device, the operation of radioactive sources and emergency preparedness. Conclusion It is necessary to strictly supervise the issuance of licenses, strengthen internal radiation safety management and evaluation, and focus on emergency training and nuclear safety culture construction.
  • XIAO Jun, ZHANG Yanjun, CHEN Qunhua, WANG Hongfeng
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    Objective To measure and evaluate the radioactivity level of negative ion paint-free panel for indoor decorative materials containing radioactive substances, to find out the problems, and to explore the solutions and countermeasures. Methods The specific activity and gamma dose rate of indoor environment were monitored and analyzed according to national standards. Results The radioactivity of the negative ion paint-free panel met the requirements of Class A decoration materials in GB 6566-2010. But the radiation level of indoor environment caused by the negative ion paint-free panel and the personal additional dose to users significantly increased. Conclusion As the influence of low dose radiation on personal mental health can not be ignored, it is necessary to strengthen the supervision of products containing radioactive substances, carefully evaluate and judge the justification of products.
  • XIE Lianke, ZANG Yuwei, GUO Zhaofeng, MA Xingang, GONG Quanquan, YIN Jianguang
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    Objective To study the distribution of the electromagnetic environment in ultra-high voltage converter station and the influence of electromagnetic radiation generated by a ±800 kV converter station on the environment. Methods The electromagnetic environment of sensitive points and field boundary points in ±800 kV converter station were measured and analyzed. Results The results showed that the maximum synthetic field strength of ±800 kV converter station was less than 30 kV/m, the power frequency electric field was less than 4kV/m, and the power frequency magnetic field strength wss less than 100 μT. Conclusion The electromagnetic environment level of ±800kV converter station meets all standards.
  • HUANG Wei, GAO Peng, GONG Zengyan
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    Objective To establish a method for the determination of Uranium in water by microwave digestion and ICP-MS, and compare it with the liquid laser fluorescence method. Methods The Uranium contents in different water samples were determined by the ICP-MS after microwave digestion and the liquid laser fluorescence method. Results The detection limits of liquid laser fluorescence and ICP-MS were 0.021 μg·L-1 and 0.003 μg·L-1, respectively. The standard deviations of the two measurements were 1.20%~4.24% and 0.78%~3.46%, and their precisions was 3.02% and 0.71%, respectively. The actual samples were analyzed by the two methods, their results were in good agreement. Conclusion The detection limit of Uranium in water by ICP-MS is low, and its precision and accuracy are higher, but the instrument is expensive. Therefore, each laboratory should select the analysis method according to the actual conditions and the Uranium content of the sample.
  • WANG Zhen, SANG Wenjuan, YU Hailin
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    Objective To investigate the radioactivity in raw materials and products in zircon sand processing plants and to grasp the distribution of radioactivity in production processes and its impact on the environment, so as to provide scientific basis for strengthening environmental management and pollution prevention. Methods The absorbed dose rate in air from γ radiation of raw materials and products were monitored in situ, and the contents of natural radionuclides in raw materials, products and soil samples collected were analyzed. Results The absorbed dose rates of zircon sand, zirconia and silicon dioxide were 16~28 times higher than that ofthe local natural background. 238U contents in some samples exceeded the exemption level. The contents of natural radionuclides in the soil samples in the plant area were higher than those in the soil samples outside the plant.The annual effective dose of the worker received from the external radiation was estimated to be 1.24 mSv. Conclusion The radioactivity level of materials in zircon sand processing is obviously higher than the environmental background level, and it will affect the soil in the plant area. It is necessary to strengthen the management of processing processes and establish a good safety culture to prevent the spread of pollution.
  • CHEN Baocai, PENG Chong, ZHOU Hualong, HE Xianwen, LU Ying
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    Objective This study aims to evaluate the level of 90Sr inthe environment around the Fangchenggang Nuclear Power Plant during its initial operation period. Methods This investigation is conducted according to the national standard of 《Technical criteria of radiation environment monitoring》(HJ/T 61-2001). Results The radioactivity concentration of 90Sr in the sampleswas measured, which were collected during 2016-2018 from the environment of Fangchenggang Nuclear Power Plant,Guangxi,China. The resultsarelisted as follows:forthe atmospheric dust, the range is 0.151~3.78 mBq/m2.d, the rain water 0.317~6.48 mBq/L,the drinking water<0.350~2.38 mBq/L,the ground water 0.403~3.18 mBq/L,the surface water<0.353~4.59 mBq/L, the seawater 0.526~4.16 mBq/L, the dry soil 0.160~3.62 Bq/kg,the dry shore sediments 0.185~0.841 Bq/kg,the dry soil of tideland 0.363~1.32 Bq/kg,and the dry seawater sediment 0.180~0.736 Bq/kg,the fresh biology<0.0160~5.54 Bq/kg·fresh. Conclusion The radioactivity level of 90Sr around the Fangchenggang nuclear power plant is within the normal range and close to those in other regions of China.
  • TANG Haiying, GUO Xianhua, ZHANG Qing, LIAO Jinghui, ZHANG Lin
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    Selecting several special issues planned and published by the Chinese Journal of Radiological Medicine and Protection, which highlight the significant scientific research progress in the field of radiological medicine and protection and the theoretical innovations of biological effects of ionizing radiation in China, this paper discusses how to improve the academic achievements communication based on an outstanding journal from the following aspects:focusing on the specialty characteristics, concreting the academic achievements, relying on the superior resources to guide the development of the journal, highlighting the purpose and strengthening the style and characteristics of the journal.
  • HUO Menghui, SU Kaijun, JIAO Ling, YIN Chen, WANG Fang, ZHANG Wenyi
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    Objective To understand radiation worker's awareness of radiation protection, enhance their awareness of radiation protection, and reduce the damage of radiation to themselves and others. Methods A total of 627 radiological workers were selected from different regions of China, among which a certain number of workers were randomly selected from the stratified cluster sampling in Tianjin and other regions. The investigators in Tianjin were given out and retrieved on site, while the rest of other areas were filled in through online anonymous forms. Results Radiation workers generally pay more attention to the knowledge of radiation protection, but have a low level of basic knowledge of radiation protection. In addition, in some units, radiation-related staff failed to carry out radiological physical health examination before taking part in the work. Some units lack oversight and contingency plans for radiological accidents. Conclusion The basic knowledge of radiation protection of radiological workers is relatively deficient, which has nothing to do with their educational background. Therefore the unit needs to improve the training methods or add corresponding lectures. According to the different job categories of medical and non-medical, the corresponding protection education and training should be carried out to improve the level of radiation protection. It is necessary to pay attention to the wearing of individual dosimeters and the physical examination of radiological workers.
  • SHEN Lijun, DONG Zhenjun, CHANG Jin, YIN Junqing, FENG Dongying
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    Objective Through the selection of 75 administrative penalties typical cases of radiological health in Beijing-Tianjin-Hebei from 2015 to 2017, to analyze the main problems and causes in the radiological health supervision and law enforcement cases as well as the investigation and penalty process, so as to provide countermeasures and data support for radiological health management. Methods The typical cases of radiological health administrative punishment in recent three years were selected from Beijing, Tianjin and Hebei, and the statistical analysis was carried out from the aspects of geographical distribution, punishment subject, punishment cause and punishment type. Results There were 75 typical cases of administrative punishment on radiological health supervision in Beijing-Tianjin-Hebei region from 2015 to 2017, among which 35 cases (46.7%) were investigated and handled in 2016, the main body of punishment was the first and above hospitals (59cases), accounting for 78.7%; The punishment cases were mainly due to the equipment sites not tested or radiological diagnosis and construction project not completed and accepted (accounting for 26.7%); 31 cases (accounting for 44.9%) were fined under 3 000 yuan. Conclusion It is necessary to fully understand the importance of radiological health supervision, improve the relevant laws and regulations on radiological health as soon as possible, increase the administrative punishment of radiological health, strengthen the training and publicity of radiology knowledge and laws and regulations, then improve the quality and level of radiological health supervision and law enforcement.
  • ZHANG Kongyuan, XING Yuzhi, SHENG Zhixin, ZHANG Xiaoyi
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    Objective To establish dose distribution characteristics and isodose curves of 125I seed plane implantation using computer three-dimensional treatment planning system (3D-TPS) and geometric principles, and to explore the value of dose distribution in hexagonal plane implantationmodel. Methods By computer treatment planning system, dose characteristics of 125I seeds with equilateral triangular, square and hexagonal distributions were created, dose distribution curves of 1 000, 3 000, 6 000, 9 000, 12 000, 15 000 and 20 000 cGy were attained, and dose distribution at 0, 0.5, 1.0, 1.5, 2.0 and 2.5 cm distances from the implantation center were calculated. The hexagonal figure with 1 cm, 2 cm, 3 cm and 4 cm edge lengths was drawn using geometric principles, and the points, including those added on the edges larger than or equal to 2 cm and the central point were connected. Results The three-dimensional particle therapy planning system could be used to simulate the isodose curve distribution under plane implantation. Under the conditions of equilateral triangle, square and hexagon, when the distance between the particle and the center is more than 2.0 cm and 2.5 cm, and the central dose is less than 10 Gy, it is necessary to increase the central dose of the particle. The connection lines of any three adjacent points in the drawn hexagon all constitute equilateral triangle, and the edge length is 1 cm. Conclusion The distribution model of hexagonal center plus a particle is most accordant with the dose uniform distribution through analyzing the isodose curve and geometric principle of 125I seed implantation distribution with different plane geometry. And this would have special meaning for clinical 125I seed implantation treatment of tumors.
  • GU Qing, FENG Wei, LAI Xiaojing, LIN Xiao, YU Xiaofu, ZHENG Xiao
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    Objective Radiotherapy is one of the most important palliative treatments for unresectable advanced malignant thymoma. The purpose of this study was to provide a theoretical basis for the selection of advanced malignant thymoma radiotherapy technology by comparing the dosimetric parameters of IMRT, VMAT and TOMO plans. Methods 9 patients with unresectable advanced malignant thymoma were retrospectively selected for this dosimetric study. Target volume and organs at risk (OARs) were delineated and transmitted to the Raystation and TOMO planning system. RTOG1106 was used for districting the doses to the OARs. The isodose curve, dose-volume histograms (DVHs), conformal index (CI), homogenecity index (HI) and the doses to the OARs were calculated in each treatment scheme. Results The three radiotherapy plans of 9 patients could suffice the demand of prescription dose and dose limits for OARs. For PGTV, the conformality and homogeneity dose distribution of the TOMO group were superior than those of the IMRT or VMAT groups. The median V5 to total lungs of TOMO group (V5=41.858%) was significantly decreased compared to plans by IMRT (V5=45.9%, P=0.038) and VMAT (V5=48.86%, P=0.015). The median V20 to total lungs was reduced by TOMO (V20=20.25%) compared to IMRT (V20=23.78%, P=0.0105). The median V40 to heart by TOMO (V20=23.576%) was significantly less than that by VMAT (V40=27.81%, P=0.025). The median of maximum doses to spinal cord was also reduced by TOMO (Dmax=37.65 Gy) when compared to IMRT (Dmax=38.39 Gy, P=0.021) or VMAT (Dmax=39.6 Gy, P=0.008), respectively. Conclusion TOMO plan for unresectable advanced malignant thymoma could achieve better conformal target coverage and homogeneity dose distribution than IMRT or VMAT. TOMO also provides better OARs protection than IMRT or VMAT.