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  • 28 June 2015 Volume 24 Issue 3
      
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  • Studies of Field Strength Distribution and Protection Strategy on Electromagnetic Radiation of Radar
    WANG Xiu-de, LI Qi-hui, TANG Mu-tao, WANG Qian, GU Qia-min
    2015, 24(3): 193-195,198. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.001
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    Objective To investigate the electromagnetic radiation distribution of radar for establishing hygienic protection strategy. Methods The power densities were measured in work areas and surroundings of radar stations by electromagnetic field meter according to the relative military standards, and the safe distances from antenna systems were calculated. Results The power densities of 2 points inside radar rooms and 3 points outside rooms exceeded the exposure limits in work areas,while 1 point in inhabitant areas exceeded the environment limits in 5 radar stations measured. All buildings surrounding radar stations met the requirements of safe distances. Conclusion The radiation in radar room is mainly from the radar equipment leak. But in surrounding environment, the radiation comes from antenna, and varieties with the antenna rotating. The protection strategy should include antenna construction, work-area management, equipment safeguard and occupational health guard.
  • Effects of 137Cs Gamma Irradiation on The Hematopoietic and Immune Function in Mice
    ZHANG Li-juan, LU Lu, WANG Yue-ying, LI De-guan, ZHANG Jun-ling, MENG Ai-min, MA Rui
    2015, 24(3): 196-198. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.002
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    Objective To observe the effect of irradiation on the hematopoietic and immune function of four kinds of mice, IRM-2、ICR、615 and C57BL/6J. Methods After the 4.0Gy radiation with 137Cs gamma ray, respectively peripheral blood classification was performed, bone marrow nucleated cells(BMNC) count and visceral index of the four kinds of mice were measured and the phagocytic function of peritoneal macrophages on chicken red blood cells were tested. Results The total number of WBC,the number of BMNC and macrophage phagocytosis rate of IRM-2 are higher than those of other strains, and the differences between IRM-2 and 615 or ICR or C57BL/6J were statistically significant(P < 0.01). The classification of the four kinds of mice white blood cells is basically consistent. Fourth weeks after irradiation, the differences in the number of WBC and BMNC in IRM-2 were statistically significant compared with 615 or ICR or C57BL/6J (P < 0.01). Conclusion IRM-2 mice have better hematopoietic and immune functions, and are good animal model applied in the experimental study.
  • Synthesis and Hypoxic Radiosensitization of N-(5-Nitroindazole-3-Formyl) Phenylalanine Sodium
    WANG Hao, ZHOU Xiao-liang, ZHOU Ze-wei, SONG Na-ling
    2015, 24(3): 199-201. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.003
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    Objective To synthesize the N-(5-nitroindazole-3-formyl) phenylalanine sodium and investigate its hypoxic radiosensitization. Methods To synthesize the target compound using condensing agents, and investigated its radiosensitization under hypoxia using in vitro and in vivo models. Results The synthesis and structure of the target compound were confirmed. Cell and xenograft models showed that the compound had a certain radiosensitizing activity. Conclusion N-(5-nitroindazole-3-formyl) phenylalanine sodium had good radiosensitizing activity and was worthy of further studing.
  • The Impact Analysis of Low-Dose Ionizing Radiation on Eye Lens of Occupational Population
    YANG Fei, LIU Zhu, WANG Meng-jie, ZHOU Xiao-jing, ZHAO Ying, LI Jia-yuan
    2015, 24(3): 202-204,212. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.004
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    Objective To explore the impact on eye lens among workers exposed to low-dose ionizing radiation. Methods 1032 subjects were used to analyze the correlation between the accumulated radiation doses and eye lens damage. Wilcoxon Rank, χ2 Test and Multivariate Logistic Regression were implemented with SPSS16.0 software. Results Both in male,female and those over 35 years, the abnormal rate of Eye Lens in accumulated doses over 11.369 mSv was higher than that of the group with doses less than 2.009 mSv (P < 0.05). There was no statistical difference between the eye lens distribution in male and female groups with the stratification factor of accumulated doses (P > 0.05). And there was no statistically significant difference between the eye lens distribution in thoser under 35 years and over 35 years with the stratification factor of accumulated doses (P > 0.05). The accumulated dose which was more than 11.369mSv was the major risk factor for the damage of Eye Lens with controlling confounding factors such as gender, work-type and age(OR=7.78,95% CI:1.93~31.38). Conclusion Long-term exposure to low-dose ionizing radiation has certain damage on Eye Lens of occupational population.
  • New Progress in the Standard for Radiological Health
    CHEN Er-dong, JU Jin-xin, XUE Ru
    2015, 24(3): 205-207. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.005
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    Objective To introduce new progress of the standard for radiological health in our country and related standardization work. Methods Research status of standard for radiological health and standardization work since the establishment of the seventh committee were analyzed and summarized. Results New progress in the professional committee of standard for radiological health、status of standard for radiological health、standardization work of radiological health and existing problems was elaborated. Conclusion The analysis and summary are helpful to the standardization work of radiological health, the implementation of the standardizing construction, and meeting the requirements of sustainable development on the health standard.
  • Methods and Discussion of the Leakage Radiation of Radiological Protection Standard of Electron Accelerator in Radiotherapy
    YANG Shu-hui, GAO Ze-yu, LU Feng, ZHANG Lin, ZHU Jian-guo
    2015, 24(3): 208-211. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.006
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    Objective To find out the existing problems and grope for the rule and provide suggestions and opinions for GBZ 126-2011 through measuring and analyzing the X-ray or neutron leakage radiation levels inside the M area and outside the M area of 17medical electron accelerators. Methods 17 medical electron accelerators are measured in this experiment according to the measure method of GBZ 126-2011. Results The maximum and the average ratio of X-ray leakage radiation of 17 medical accelerators inside the M area meet the requirement of GBZ 126-2011. The difference between the results of the measurement is very small and the requirement of GBZ 126-2011 would be at least an order of magnitude higher than the results. The maximum and the average ratio of X-ray leakage radiation of 17 medical accelerators outside the M area meet the requirement of GBZ 126-2011,but the results of the measurement is very close to the requirement of GBZ 126-2011. The maximum ratio of neutron leakage radiation of 7 medical accelerators outside the M area meet the requirement of GBZ 126-2011; The average ratio of neutron leakage radiation of 2 accelerators does not meet the requirement of GBZ126-2011, while the data of the others meet the requirement of GBZ 126-2011,the results of the measurement is also close to the requirement of GBZ 126-2011,especially the date of 15 MV accelerator. The thermoluminescent dosemeter as detector to test leakage radiation of X-ray is simple inside the M area,but no matter which method you adopt,the method to test the leakage radiation of X-ray and neutron is complex outside the M area. Conclusion To provide plain suggestions and opinions for leakage radiation part and the method of the Leakage Radiation of Radiological Protection Standard of Electron Accelerator in Radiotherapy (GBZ 126-2011).
  • Implications for Occupational Radiation Protection of the Interventional Radiology Staff of the New Dose Limit for The Lens of The Eye
    XUE Ru, CHEN Er-dong, JU Jin-xin
    2015, 24(3): 223-226. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.013
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    Objective To provide appropriate advice on improving the radiation protection of the interventional radiology staff. Methods Synthesizing the relevant standards and the results of related researches to analyze and discuss the potential implications. Results For interventional radiology staff,the monitoring of the dose to the lens of the eye should be routine. Personal protective equipment should be provided properly, as well as the necessary training. Conclusion The occupational radiation protection of the interventional radiology staff in our country needs to be improved.
  • Estimation of Radon Concentration in office and Doses Received by Residents in Shijiazhuang City
    ZHOU Kai-jian, Zhang Jing-zhan, DONG Jun-shan, ZHAO Zhi-hui
    2015, 24(3): 227-229. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.014
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    Objective To test the level of office radon concentration of residential areas in Shijiazhuang City in different floors, building materials and construction age and to analyze its influencing factors in order to estimates the exposure doses received by the residents. Methods solid state nuclear track method was used measure the cumulative dose of radon concentration. Results The mean concentration of office radon concentration was (32.12 ±13.74) Bq·m-3 in Shijiazhuang City. The highest values were in the reinforced concrete cottage. The dose caused by the radiation was 0.58 mSv/a. Conclusion The level of office radon concentration of residential areas in Shijiazhuang City is a normal natural backgrood level. Building materials are the major factors that affect the office radon concentration. Selection of appropriate materials for construction and effective ventilation can reduce radiation doses received by residents, thus reducing its negative impacts on human health.
  • The Staff Dose Caused by Indoor Radon and γ Radiation Dose Levels in Hospitals of Nanning City
    LIU Chang-zheng, SHANG Bing, WU Yun-yun, ZHU Li
    2015, 24(3): 232-233. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.016
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    Objective To understand indoor radon and γ exposure rate levels in Department of Radiology and Nuclear Medicine of Hospital of Nanning City to estimate radiation doses of staff, and to provide a basis data for radiation protection management. Methods Using ATD radon monitors and FH40G environmental γ dose rate meter to measure radon concentration and γ dose rate indoor and outdoor. Results The staffs in Nuclear medicine, radiology underground and surface workplace, and residents affected by radiation doses are 1.98 mSv, 1.84 mSv, 1.62 mSv, 1.48 mSv and 1.49 mSv respectively. Conclusion The additional dose for Nuclear Medicine staffs related with radioisotopes majorly from the amount and the protective conditions. Radiology staff doses are mainly caused by the elevated radon contamination.
  • The Investigation of Radiation Level in a Coal Preparation Plant
    LIANG Jing, LIAN De-xing, ZHU Wei-guo, ZHANG Qi, HOU Chang-song
    2015, 24(3): 237-239. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.018
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    Objective The dose equivalent rate of densitometer workplace was detected and analyzed in a coal preparation plant to help the radioactive protection and staff health. Methods The γ dose rate instrument was used to detect the workplace dose equivalent rate of densitometer as standard requirements. Results The dose equivalent rate from the radioactive source container 10 cm and 100 cm were 4.19~21.1 μSv/h and 0.30~3.47 μSv/h, which from the detectors 5 cm and 100 cm were 11.8~465 μSv/h and 0.53~54.5 μSv/h, when the switches were on without materials in channels. Conclusion The levels of dose equivalent rate were higher than those of the standard requirements in some densitometer workplace when the switches were on without materials in channels. In order to protect staff health, there should be some measures to be taken such as closing the switch of radioactive source container timely in no production, or far away from the densitometer workplace.
  • Measurement and Analysis on Radiation Protection of A 252Cf neutron Afterloading Radiotherapy Room
    DENG Jun, SU Yin-ping, REN Fu-li, SONG Yan-chao, WANG Tuo, GUO Wen
    2015, 24(3): 240-242. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.020
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    Objective To analyze the entity protective effect of 252Cf neutron afterloading radiotherapy room as well as distribution and changing rule of neutron, γ radiation level in the maze, and to accumulate experimental data and experience of radiation protection as well as to provide a scientific basis for the control of occupational exposure by field measurement. Methods When the 252Cf neutron afterloader was on operation, neutron, γ radiation level at concerned points outside entity shielding wall and inside the maze were measured by neutron ambient dose meter and X-γ dose rate meter, respectively. Besides, the law among neutron, γ radiation level and location of concerned points were analyzed based on the nonlinear regression model, the entity protective effect of the radiotherapy room as well as the changing rule of neutron, γ radiation level at concerned points in the maze were also studied. Results The result shows that the neutron, γ radiation level outside the shield of 252Cf neutron afterloading radiotherapy room were around the background level. Meanwhile, neutron, γ radiation level in the radiotherapy room shows exponential decay trend with the increase of the distance to the entrance. Conclusion The protective effect of the 252Cf neutron afterloading radiotherapy room meets the relevant requirements. Long maze setting is an effective way to lower the radiation dose at the radiotherapy room door.
  • Analysis of Surveillance on Radiation Protection from Medical Institutions in Shanghai Fengxian District
    WANG Zhong-liang, CHEN Tao, CHEN Jie, CHEN Chun-hui, ZHU Guo-ying
    2015, 24(3): 262-264. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.032
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    Objective To understand the status of radiation protection of medical institutions, in order to provide scientific basis for the supervision and management of radiation protection, and to protect the health rights and interests of the radiation medical staff, patient and the public's. Methods Selective inspection data of radiation protection from 20 medical institutions in Shanghai Fengxian district were collected and analyzed. The X-ray dose rate was detected by means of real-time measuring method for medical diagnostic X-ray room. Results The sampling 20 medical institutions are in interventional radiology diagnosis and treatment and conventional X-ray imaging diagnosis. The surveillance result of radiation protection of medical institutions was gerally good. A total of 1318 sampling points from 35 medical X-ray diagnostic rooms were inspected, 1311 points were qualified and the qualified rates were 99.5%. Conclusion The radiation protection of the sampling 20 medical institutions in Shanghai Fengxian district is currently at a high level. But the dose rate in the part of X-ray diagnostic room is over the standard limit due to the aging of protective facilities. Regular supervision and inspection, shielding facilities maintenance is necessary for radiation protection.
  • Investigation and Analysis of the Radiation Environmental Impact of Uranium Mining and Metallurgy Retirement Places of Yili Xinjiang
    ZHAO Qi-wen, WANG Guo-quan
    2015, 24(3): 271-272,276. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.036
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    Objective To investigate the radiation environment of uranium mining and metallurgy retirement places of Yili Xinjiang. Methods By the field investigation and monitoring, the radiation environment of uranium mining and metallurgy retirement places were monitored to analyze and evaluae of the environmental radiation level. Results the radiation environment of uranium mining and metallurgy retirement places that were investigated are of the local background level, the Ra-226 content of some samples in the retirement places of the original B mine, the original factory C and the original D mine. Conclusion The retirement places of the original D mine needs further treatment.
  • Early Countermeasures Analysis of and of Japan's Nuclear Crisis
    LI Wei, SUN Jun, YANG Yun-fu
    2015, 24(3): 273-276. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.037
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    Objective To provide suggestions for early countermeasure for the nuclear crisis to ensure the plan for early countermeasure reasonable, and to be carried out orderly. Methods It was done according to the domestic and foreign related laws,regulations,standards and technical documents, combined with the research and analysis of early Japan's Fukushima nuclear power plant accident countermeasures of in recent years. Results The characteristics of nuclear crisis early countermeasure were clarified. The decision and implementation process of early countermeasure were analyzed. Conclusion Early countermeasures should be paid more attention in the off-site emergency of nuclear crisis,we must keep rational and calm when we implement countermeasures of evacuation, concealment and iodine-prophylaxis.
  • Analysis in Site Disposal Technique of Medical Response to Nuclear and Radiological Emergency
    FU Xi-ming, YUAN Long
    2015, 24(3): 277-280. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.038
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    Objective To analyze and discuss the site disposal techniques of medical response to nuclear and radiological emergency. Methods Through summarizing and evaluating experience of several exercises of medical response to nuclear and radiological emergency in China, combined with technical reports issued by the International Atomic Energy Agency (IAEA), the key points of site disposal techniques are discussed. Results It is found that we china the national standards of site disposal techniques of medical response to nuclear and radiological emergency. The site disposal technical flow for medical response to nuclear and radiological emergency was provided, and the aspects which should be paid attention to and be improved was put formard. Conclusion Through the discussion of disposal technique in emergency, it is hoped that the operational capability of response teams for nuclear and radiological emergency in China can be improved. It is suggested that the national standards for disposal techniques of medical response to nuclear and radiological emergency should be drawn up or revised in order to improve the capability of medical response to nuclear and radiological emergency in China.
  • Methods for Generation and Control of Gaseous Radioactive Iodine
    ZHAO Chao, TANG Fang-dong, HE Lin-feng, LU Xiao-jun, ZHUO Wei-hai
    2015, 24(3): 290-292. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.044
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    The generation of gaseous 131I is a key technique for building standard reference of gaseous 131I activity concentration. In this study, gaseous iodine (I2) is produced from iodide solution through redox reaction. The production of radioactive gaseous iodine can be adjusted by regulating the activity of the iodide solution in the redox reaction. The productivity of gaseous iodine was determined to be about 78.0% ±7.9% (95% confidence interval) which is relatively stable when using Fe2 (SO4)3 as oxidant under certain reaction condition.
  • Gamma Knife Quality Control of Radiation Field
    LIU Li-ming, GUO Zhao-hui, CHENG Jin-sheng
    2015, 24(3): 296-298. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.046
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    Objective Through the gamma knife radiation field measurements, to understand the gamma knife radiation field size deviation and the penumbra of the focal plane. Methods Film method was used to measuring rotating gamma knife and static gamma knife, a total of 4 sets of gamma knife radiation field. Results Gamma knife radiation field size and nominal value maximum deviation is 1.3 mm. Radiation Field on the focal plane width of penumbra collimator penumbra maximum deviation is 3.9 mm at 4# collimator, 8# collimator penumbra maximum deviation is 5.2 mm, 14# collimator penumbra maximum deviation is 9.0 mm, 16# collimator penumbra maximum deviation is 9.9 mm, 18# collimator penumbra maximum deviation is 10.9 mm are 22# collimator penumbra maximum deviation is 13.0 mm. Conclusion The measurement of gamma knife radiation field size deviation and the penumbra of the focal plane are less than the national standard which can meet the normal use.
  • The Application Value of Multislice Helical CT Myocardial Perfusion in Diagnosis of Coronary Heart Disease Ischemic Myocardium
    ZHENG Bo, ZHANG Xin-yi, YIN Zu-dong
    2015, 24(3): 303-305. https://doi.org/10.13491/j.cnki.issn.1004-714x.2015.03.049
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    Objective To explore the application value of multislice helical ct myocardial perfusion in diagnosis of coronary heart disease ischemic myocardium and provides a reference for future clinical diagnosis and treatment. Methods This study selects the 26 reversible myocardial ischemia coronary heart disease patients who were diagnosed through nuclein perfusion imaging and were treated in our hospital from April 2011 to May 2013. They are the observation group. The control group includes 15 cases of normal people. All cases are diagnosed by multislice helical CT myocardial perfusion. According to the changes of resting load perfusion images, the study evaluates the myocardial perfusion defect nature and measures the myocardial density of cases in the two groups. Finally the study compares and analyzes the measuring results of the two groups. Results The contrast of the scanning stage myocardial density measurements corresponding to the resting and load in the control group is not significant(P > 0.05). The difference is not statistically significant. The contrast of the scanning stage myocardial density measurements corresponding to the resting and load in the observation group is significant(P > 0.05). The difference is statistically significant. The contrast of myocardial density measurements in the plain scan and resting late 30s scan of the observation group and the control group is not significant(P > 0.05). The difference is not statistically significant. The contrasts of myocardial density measurements in the rest period are significant(P < 0.05). The differences are statistically significant. Conclusion Multislice helical ct myocardial perfusion diagnosis can identify the abnormalities of reversible myocardial perfusion effectively. It has high consistency with the diagnosis results of nuclein perfusion imaging. It can provide accurate myocardial circulation blood flow information. It is of high value in clinical application and is worthy applying and be promoted widely in practice.