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Table of Content

    20 January 2018 Volume 38 Issue 1
      
    Analysis of 210Po in water samples from some NORM industries along Yangtze River
    LI Jinfeng, PAN Jingshun, WANG Chuangao, HUANG Zhijun, LIU Weifu, LI Xiaoyun, CHEN Ling
    RADIATION PROTECTION. 2018, 38(1):  1-7. 
    Abstract ( 95 )   PDF (859KB) ( 91 )  
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    The radiation exposure received by mankind mainly comes from natural radiation. This study investigated the levels of 210Po in water samples from some NORM industries along the Yangtze River. The activities of 210Po in the effluent from coal-fired power plants, a cement plant, an iron and steel making plant and an iron ore were (0.93—4.76)×10-3 Bq/L,(1.12±0.07)×10-2 Bq/L,(9.89±0.78)×10-3 Bq/L and (2.17±0.21) Bq/L, which were all in fluctuation range of 210Po concentrations in the Yangtze River. The activities of 210Po in the effluent and rainwater from rare earth plants were as high as (1.03—1.40)×10-1 Bq/L and (3.05±0.04)×10-1 Bq/L, which were two orders of magnitude higher than the background level. This should be paid special attention and needs further research.
    The activity concentraction of 210Pb and 210Po in Hangzhou atmosphere and induced public dose assessment
    CAO Zhonggang, YANG Yang, WANG Lili, WANG Kebin
    RADIATION PROTECTION. 2018, 38(1):  8-14. 
    Abstract ( 83 )   PDF (1561KB) ( 133 )  
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    210Pb and 210Po in atmosphere are mainly from the decay of radon in surface soil on the earth, which are the last two long-lived daughter radionuclides in uranium decay chain. A method for analysis of 210Pb using 206Pb as carrier following the sample separation by ion exchange was developed to determine the activity concentrations of 210Pb and 210Po in atmosphere; and a method for the analysis of 210Po employing 209Po as tracer and counted by α spectrometer was developed. The 210Pb and 210Po concentrations in atmospheric aerosol in Hangzhou were carried out. Continuous monitoring results in 2012 showed the average 210Pb concentration was (1.31±0.69) mBq/m3, ranging from 0.12 to 2.74 mBq/m3. The average 210Po concentration was (0.29±0.18) mBq/m3,ranging from 0.06 to 0.89 mBq/m3. The 210Pb and 210Po concentrations in Hangzhou were comparable with other cities in China, while one order of magnitude higher than the American and European cities. Public committed effective dose by inhalation from atmospheric 210Pb and 210Po was 1.53 to 13.78 μSv/y, with an average value of 7.00 μSv/y.
    Contents of 210Po in some aquatic organisms and its distribution in different parts of shrimp’s bodies
    LI Pengxiang, LI Zhou, ZHANG Jing, GAO Zequan, WANG Ruijun, SONG Qinnan, HAN Yuhu, MENG Liping
    RADIATION PROTECTION. 2018, 38(1):  15-18. 
    Abstract ( 64 )   PDF (980KB) ( 152 )  
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    Concentrations of 210Po in 17 kinds of aquatic organisms were determined by an isotope tracing method, and 210Po concentrations in different parts of shrimps’ bodies were also measured. The concentrations of 210Po in edible parts of aquatic organisms were 0.15-34.8 Bq/kg of fresh weight, and the variations between different aquatic organisms were large. Aquatic organisms of crustaceans, cephalopods, and shellfishes have strong enrichment capability for 210Po, and especially the 210Po concentrations in oysters, octopus, crab,squid were 34.8, 25.0, 20.3, and 17.2 Bq/kg of fresh weight respectively, which are higher than our national limit for the 210Po concentration in food. 210Po concentrations in different parts of shrimp’s bodies presented a distribution pattern: the highest in heads, moderate in shells, and the lowest in meats.
    Real-time computation and visualization of 3D radiation field for nuclear reactor decommissioning scene
    ZHANG Yongling, HU Yifei, LIU Meng, DAI Bo, ZHANG Hangzhou, ZHUANG Qianping
    RADIATION PROTECTION. 2018, 38(1):  19-25. 
    Abstract ( 214 )   PDF (2213KB) ( 555 )  
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    A prototype 3D simulation system for reactor decommissioning based on the DELMIA and VIRTOOLS was built. Based on this simulation system, the 3D radiation field computation and visualization program were proposed by combining independent simulation system and database with computation core. Computation model of 3D radiation field was based on the point-kernel method and the polynomial fitting formula between energy logarithm and translation factor was acquired. In the model, the shielding and self-absorption of devices were considered, and the computing errors of the radiation level at key points were less than ten times of the measuring data. The computation software of 3D radiation field was programmed based on the software of VS and SQL server. Dynamic calculation and data refresh of 3D radiation field were realized. Computation model of personal dose based on walking path was proposed and visual display was realized.
    Analysis of radiation level in soil around coal-fired power plants in Harbin
    LIU Chunyu, YU Yang
    RADIATION PROTECTION. 2018, 38(1):  26-32. 
    Abstract ( 129 )   PDF (1965KB) ( 130 )  
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    Radionuclides can accumulate in fly ash and slag in the process of coal burning at different levels and fall into the soil resulting in radioactive contamination. The sampling points were located within 1 km to the Qunli and Hulan coal-fired power plants, and each sampling point was divided into three layers of different depth: A layer for 0—10 cm, B layer for 10—20 cm, and C layer for 20—30 cm. The natural radionuclides in soil samples were measured by high-purity germanium gamma spectrometer, and the specific activities of 238U, 232Th, 226Ra and 40K in the soil surrounding the coal-fired power plants were analyzed and compared with the measurement results of natural radionuclides in soils from the Heilongjiang province. Results showed that the long-term operation of the coal-fired power plants has increased the radiation levels, but it is still below the national standards.
    Radiation protection evaluation of industrial cable electron irradiation accelerator
    ZHONG Chunming, YUE Zhonghui, ZHANG Xin
    RADIATION PROTECTION. 2018, 38(1):  33-37. 
    Abstract ( 109 )   PDF (1615KB) ( 201 )  
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    Radiation protection evaluation of 3.0 MeV electronic accelerator generator room was conducted in a cable company in the Hengyang city. According to the protection evaluation requirements and the design of the generator room, source of radiation in the generator was analyzed and the shielding effectiveness was theoretically calculated. Combining the theoretically shielding effectiveness and actual monitoring results, the shielding design of electron irradiation accelerator room and radiation protection facilities meet the requirements of the state regulations.
    Performance study of iodine adsorbers used in emergency fresh air systems of main control rooms under severe accident conditions
    WANG Kunjun, ZHANG Xueping, QIAO Taifei, MA Ying, SHI Yingxia, QIU Dangui
    RADIATION PROTECTION. 2018, 38(1):  38-44. 
    Abstract ( 102 )   PDF (1936KB) ( 97 )  
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    In order to study the efficiency variation of iodine adsorbers used in main control rooms under accident conditions, poisoning, aging, irradiation, and efficiency variation experiments of impregnated activated carbon were carried out. Basing on combination of various experimental factors, long-term efficiency variation tests were designed and carried out under two condition sets of (70±1) ℃ temperature with (40±2)% relative humidity, and (44±1) ℃ temperature with (95±1.5)% relative humidity, using three kinds of activated carbon samples with initial efficiencies of 99.90%, 99.97%, and 99.98%. Experimental results showed natural aging phenomena in activated carbon samples, and acetic acid and other substances could accelerate the aging process of activated carbon. Irradiation had no effect on the efficiency of impregnated activated carbon to remove radioactive methyl iodide. Under severe accident conditions, the efficiencies of activated carbon samples had no decrease within 168 hours.
    Development of a measuring device for tritium in process
    CHANG Yu, MENG Jinhong, ZHONG Xueming, ZHANG Qingjie
    RADIATION PROTECTION. 2018, 38(1):  45-50. 
    Abstract ( 128 )   PDF (2124KB) ( 142 )  
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    Measuring device for tritium in process exhaust using ionization chamber (effective volume 11.0 mL) was developed after material selection, structure design and parameter optimization. The calibration curve was plotted with a good linearity in the range of 0.013 4%—0.168% (v). The results showed that the detection lower limit of the device was 1.35×10-4 %(v); the coefficient of variation was no more than 1.50%; and the response time was less than 10 s. The process measurement requirements were fairly met.
    Study of pilose antler peptide on learning and memory abilities of mice exposed to microwave radiation
    FAN Hongyan, WANG Yanchun, REN Kuang, LI Man, XU Yuliang, ZHONG Xiuhong, LIU Shibing, LV Shijie
    RADIATION PROTECTION. 2018, 38(1):  51-57. 
    Abstract ( 116 )   PDF (1692KB) ( 144 )  
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    To investigate the effects of pilose antler peptide on learning and memory abilities of mice exposed to microwave radiation and to study its mechanism, learning and memory impairment model of mice was induced by microwave radiation of 2 450 MHz average surface power, 10.0 mW/cm2 for 28 d. The irradiated rats were treated with 25, 50, and 100 mg/kg pilose antler peptide by subcutaneous injection for 28 d. The learning and memory ability of mice was tested by Y maze experiment from 29 d to 33 d. After Y maze experiment, all mice were decapitated on 34th d, the contents of aspartic acid (Asp)、γ-aminobutyric acid (GABA), glutamic acid (Glu) and S100B, the activities of Na+-K+-ATPase, monoamine oxidase-B (MAO-B), level of tumor necrosis factor-α(TNF-α) in the brain of were determined with ELISA, respectively. The activity of superoxide dismutase (SOD) in the brain of mice was detected with xanthine oxidaseassay. The dentate gyrus area of hippocampal organizational structure was observed and analyzed by microscope after HE staining. The results indicated that compared with the control group, the irradiation group could increase the numbers of errors in Y maze experiment, and rise the contents of GABA, S100B and TNF-α, lower the contents of Asp, Glu, increase the activity of MAO-B, lessen the activities of Na+-K+-ATPase, SOD in the brain of mice (p<0.05 or p<0.01). Compared with the irradiation group, the pilose antler peptide (50, 100 mg/kg) groups could significantly decrease the numbers of errors in Y maze experiment, and effectively reduce the contents of GABA, TNF-α and S100B, improve the activities of Na+-K+-ATPase, SOD in the brain of mice. The Pilose antler peptide (25, 50, and 100 mg/kg) groups could increase the content of Asp and Glu, lower the activity of MAO-B in the brain of mice (p<0.05 or p<0.01). Pathology found that part of cell volume grew, cytoplasm was loosened and light dyed, part of the nucleus pycnosis was seen in the irradiation group. Compared with the irradiation group, hippocampal organization structure could be improved by pilose antler peptide (100 mg/kg). Experimental results showed that pilose antler peptide (50, 100 mg/kg, for 28 days) could significantly improve the learning and memory ability of mice exposed to microwave radiation. The mechanism may be related to its enhancement of anti-oxidative actions by anti-inflammatory action, further improving levels of neurotransmitters.
    Waste minimization strategy for the Tianwan Nuclear Power Plant
    LIU Tiejun, SUN Xueqiang
    RADIATION PROTECTION. 2018, 38(1):  58-64. 
    Abstract ( 129 )   PDF (2702KB) ( 164 )  
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    There are currently four VVER nuclear power units and two improved M310 nuclear power units in the Tianwan Nuclear Power Plant. To reduce the final amount of solid waste package for disposal so to meet the waste minimization management objective, a radwaste treatment center was constructed and shared by the above six units in addition to taking measures to control the generation of radioactive wastes from sources. The radwastes are treated by drying, super-compaction and grouting process, together with adopting high integrity containers of concrete. Ascribing to the above measures, the waste volume to be disposed from one unit does not exceed 50 m3 each year under the precondition that the waste packages meet the requirements for near surface disposal. This waste treatment strategy brings good economic and social benefits, so can be used as a reference to waste minimization for nuclear power stations with multiple reactor units.
    Sorting-treatment method and practice of spent filter cartridges in nuclear power plants
    YU Dawan, XU Hongming, YANG Yongliang, GUO Xiliang
    RADIATION PROTECTION. 2018, 38(1):  65-70. 
    Abstract ( 136 )   PDF (2533KB) ( 153 )  
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    Spent filter cartridge is one of the main sources of radioactive solid wastes in nuclear power plants. In order to reduce the amount of final wastes, a sorting process for spent filter cartridges based on their surface dose rate level is essential. The spent filter cartridges of less than 2 mSv/h surface dose rate can be dried, compacted, and solidified with grouting. The spent filter cartridges of 2 mSv/h to 50 mSv/h surface dose rate need a temporary storage decay before commencing the above process. When its surface dose rate is higher than 50 mSv/h, a spent filter cartridge must be solidified directly with grouting. With the sorting-treatment method, the amount of the final waste is reduced by 21.3 m3 according to the design value and by 8 m3 according to the practical value. Radioactive waste minimization is achieved, and the cost for waste disposal is reduced to generate considerable economic and environmental benefits for nuclear power plants.
    Structure and function design of geo-information database for high-level radioactive waste disposal in China
    WANG Peng, HUANG Shutao, WANG Ju, ZHAO Yongan, WU Lun, CAI Heng, GAO Min, WANG Hongbin, WANG Shuhong, LIU Yuanlin
    RADIATION PROTECTION. 2018, 38(1):  71-79. 
    Abstract ( 84 )   PDF (4289KB) ( 278 )  
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    Geological disposal of high-level radioactive waste is a large project of long-term, complex and systematic. There will be vast amounts of data resources generated during the whole R&D process. Therefore, it is very important and necessary to establish an aided information system to manage data of HLW disposal. In this paper, based on collection of multi-source data in geoscience field and construction of multi-source geo-information database, a geological information management system for pre-selected area of HLW disposal was developed. Basic CRUD (create, retrieve, update and delete) operations can be achieved through this management system as well as full text search and download. Particularly, statistics and analysis of certain professional data can be provided.
    Discussion on construction of a radwaste management system in Haiyang Nuclear Power Plant (AP1000)
    LI Qi, GOU Quanlu, YU Xiaodong
    RADIATION PROTECTION. 2018, 38(1):  80-87. 
    Abstract ( 117 )   PDF (2598KB) ( 162 )  
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    Through the analysis of radwaste sources and its design characteristics of the radwaste treatment system combining with practical experiences of radwaste management in AP1000 of the Haiyang Nuclear Power Plant, the strategy of radwaste management, design of process routes, mode of operation management were studied to provide a suitable construction model of the radwaste management system for the AP1000 type nuclear power plant in order to achieve the minimization of radwastes.