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20 August 2014 Volume 34 Issue 4
Progresses
Assessment of Ionizing Radiation Exposure of Non-human Species: Reference Plant
Wang Huijuan, Li Jianguo, Han Baohua, Ma Binghui
RADIATION PROTECTION BULLETIN. 2014, 34(4): 1-5.
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This article compared the ECERICA method and the United States DOE GRADED method (RESRAD BIOTA) in the reference plantdose evaluation procedure aspect from the reference plant and its geometric model, dose calculation, environmental exposure hypothesis conditions, and discussed difficulties and deficiencies currently in the reference plant radiation impact assessment, and gave some advice on carrying out our ionizing radiation impactassessment research on non-human reference plant species.
Analysis of Features and Development Tendency for Nuclear Power Plant's Radiation Monitoring System
Yu Shaojie, Zhang Jing, Hao Rui
RADIATION PROTECTION BULLETIN. 2014, 34(4): 6-9.
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37
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145
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Radiation Monitoring System (RMS) is important to protect the safety of Nuclear Power Plant (NPP) workers, the public,the environment, and also the operation of nuclear power system. The paper analyses and summarizes the technical features of RMS for 2nd, 2nd-plus, and 3rd-generation Pressurized Water Reactor (PWR), discusses development tendency of itsframework, intelligence auto-alarm technology, and post-accident monitoring technology. This study will inform RMS's design, operation management, research and development of new equipment, etc.
Articles
Effects of Cytokines Combination on Acute Radiation Injury in Mice
Li Weibin, Qi Xiujun, Li Shufang, Yue Juan, Yin Jingjing, Zhang Wei, Li Jianguo, An Quan
RADIATION PROTECTION BULLETIN. 2014, 34(4): 10-15.
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27
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37
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Whole body irradiation was made with 10 Gy
60
Co gamma ray in male ICR mice to observe 30 days survival ratesin each group and measure animal weight, haemocytes, blood coagulation, weightand coefficient of organ, bone marrow nucleated cell count, micronucleus percentage after irradiation. The results show that, cytokines have significant protective effects on adiation injury in mice. (G-CSF+IL-Ⅱ+TPO) group and (G-CSF+TPO+interferon α2β) group was better than single cytokine groups among them.
A Shielding calculation Study for High Energy Industrial X-ray Flaw Detector Rooms
Chen Rongmin
RADIATION PROTECTION BULLETIN. 2014, 34(4): 16-20.
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31
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118
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Shielding calculations were performed for the room of a linear accelerator of model DZ-12/5500, with NCRP Report No. 151, GBZ/T 220.2—2009 and etc as references, to illustrate how to select a suitable calculation method to determine the optimal shielding thickness of room for industrial flaw detecting linear accelerator of energy above 10 MV. It shows that a 278 cm thick concrete shielding wallis needed in the useful beam direction, while the concrete thickness in other 3sides should be 182, 195 and 204 cm respectively. With a roof of 110 cm thick concrete, sky inverse scattering results in an extremely small dose equivalent rate in any location 20 m away from the nose of the accelerator. The ambient dose equivalent is 115.69 μSv in the Z-shaped labyrinth entrance, in which X-ray scattering and leakage, neutron irradiation, and neutron capture of X-ray give rise to 2.43, 102.96 and 10.30 μSv/week respectively. Analysis of test results upon operation indicates that calculated and tested values agree well, our calculation method and parameters selected are viable.
Immobilization of Actinides in Simulated High Level Liquid Radioactive Waste on High Silica Glass Ceramic Host
Su Wei, Wang Ling, Dou Tianjun, Pan Sheqi, Jiang Ling
RADIATION PROTECTION BULLETIN. 2014, 34(4): 21-24.
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26
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38
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High silica glass ceramic solidification was synthesized by sintering the vitreous silica at 1 200 ℃ in order to improve the performance of the glass immobilization. The testing results show that the properties of high silica glass ceramic solidification, for example, density,encapsulated capacity, the leaching rate and so on, are superior to the borosilicate glass immobilization.
A Simulation Method of Level 2 Alarm Internal Calculations for Nuclear Plant DCS
Xu Kui, Xin Huimin, Qu Ming
RADIATION PROTECTION BULLETIN. 2014, 34(4): 25-28.
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23
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87
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Internal calculation functions are designed in some nuclear plant DCS, to assist operator's operation. With Level 2 alarm internal calculation taken as a study case, a method based on data import technology is introduced. This approach combines the features of RINSIM simulationplatform, can achieve Level 2 calculation function of alarm fast and accurately. The results of utilities of RICC in practical experiments show that RICC makesLevel 2 alarm calculations easy to be imposed, and with high run-time efficiency.
12
C Irradiation Inducing Telomere Extension in HumanLymphocytes
Zhang Ruifeng, Guo Yuefeng, Dang Xuhong, Zhang Huifang
RADIATION PROTECTION BULLETIN. 2014, 34(4): 29-31.
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26
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19
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This paper is to investigate the effect of
12
C ion irradiation on telomere length in culture human lymphocytes. Culture human lymphocyte line Peng-EBV were exposed to
12
C at 0.3-0.5 Gy/min at doses of 0,0.1,0.5,1.0 and 2.0 Gy, respectively. The cells were collected at 24, 48, 72 hours after exposure, respectively. Genome DNA was extracted. Relative telomere length was measured by fluorescence quantitative PCR. The relative telomere length obviously increased at 48 and 72 hours in each dose group for exposed cells.
12
C ion irradiation may all result in telomere extension in culture human lymphocytes.
Reviews
Study Advancement for Radon Harm and Protection
Guo Yuefeng, Zhang Huifang, Zhang Ruifeng
RADIATION PROTECTION BULLETIN. 2014, 34(4): 32-35.
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30
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This paper reviews the study advancement for non cancer biologic effects and lung cancer,leukemia induced by radon inrecent years. The Chinese standards were briefly introduced for environment radon level control. It is underlined that protection of radon harm depends on environment radon level control and intensive health monitor of population living orworking in high radon exposed area.
Experiences
A Preliminary Study on Offgas-loaded Nuclides during In-drum Drying Treatment of Radioactive Concentrate from NPP
Liang Dong, Yan Xiaojun, Liu Zhaofeng, Gao Chao, Jia Meilan, An Hongxiang
RADIATION PROTECTION BULLETIN. 2014, 34(4): 36-38.
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28
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13
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In-drum drying treatment of simulatedconcentrates was conducted at variable temperatures to identify the activity concentrations and distribution of nuclides loaded in offgas during treatment of radioactive waste generated from a NPP. The result has shown that there exist detectable contents of Sr, Cs, and Co in concentrated liquid and washing liquid, with growing decreased activity concentrations with decreased drying temperatures.The loading ratios of Sr, Cs, and Co are respectively 5.14%, 0.06% and 0.05% under the boiling condition, mostly in washing liquid, whereas 2.38%, 0.03% and 0.02% respectively under non-boiling condition.
The Characterization for Decommissioning of a Radioisotope Container Cleaning Pool
Cheng shulin, Chen ling, Li hang, Qiao haitao, Tu xingming
RADIATION PROTECTION BULLETIN. 2014, 34(4): 39-42.
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24
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This paper introduces characterization activities for decommissioning of a radioisotope container cleaning pool. Issues such as lack of historical data, complicated contamination condition and the possible presence of radioactive
226
Ra sources are fully considered. A successful characterization is thus resulted. Some experiences are drawn from handling of problems met in the course.
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