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20 April 2017 Volume 37 Issue 2
Analysis of the "Three Keys" Changes in Yangjiang Nuclear Power Plant
Guo Jie, Zhen liying
RADIATION PROTECTION BULLETIN. 2017, 37(2): 1-4.
Abstract
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28
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This article introduces the changes tothe Critical groups、Critical exposure pathway、Critical nuclide (Three Keys) in Yangjiang Nuclear Power Plant since its operation in May 2013, they are causedby the changes in ambient population, environment, as well as the actual discharge of radioactive effluent from Yangjiang nuclear power plant. Through the analysis of above factors, it aims to propose new ideas for the “Three Keys”, peripheral radiation environment and effluent supervision monitoring scheme, and forthe existing sampling and monitoring methods of Yangjiang Nuclear Power Plant.
Investigation of
14
C Level in Environmental Media of Daya Bay Nuclear Power Base
Jia Yijian, Sun Hongchao
RADIATION PROTECTION BULLETIN. 2017, 37(2): 5-12.
Abstract
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20
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The monitoring results of
14
C concentration, is presented, in ambient air, rain water, surface water, groundwater, seawater and biological samples after 20 years of safe operation of DayaBay Nuclear Power Base. They show that the
14
C concentration decreaseswith the distance from Daya Bay Nuclear Power Base. When the distance increasesto about 7 km, the
14
C specific activity falls to the environmental background level.
Preliminary Study on Chronic Musculoskeletal Injury and Ergonomics ofNPP Operators
Liu Chang, Wang Wei, Chen Yuanyuan, Dong Haibei, Xu Mengjun, Liu Feng, Wu Xiaojin
RADIATION PROTECTION BULLETIN. 2017, 37(2): 13-16.
Abstract
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21
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The situation of chronic musculoskeletal injury in the control room of a nuclear power plant (NPP) was investigated and the basic dimension of the operator's seat was given based on the current seat design standards and operators' health status. The results showed that the rate of chronic musculoskeletal injury of operators was 71.57%, which was significantly different from that of ordinary radiation workers. The prevalence of chronic musculoskeletal injury in different parts was significantly different. The ergonomic chair size design was beneficial for reducing the risk of chronic musculoskeletal injury of NPP operators.
Static Adsorption of Simulated Strontium-containing Wastewater by Special Geological Cement
Lu Jiawei, Li Ning
RADIATION PROTECTION BULLETIN. 2017, 37(2): 17-21.
Abstract
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20
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Static adsorption of Strontium solution was studied in this experiment, with raw material powder of special geologicalcement used as the adsorbent. The results show that the maximum adsorption rateat equilibrium is 47.91%, the optimum adsorption time is 1.6 d, with the best performance of the cement under alkaline condition. The adsorption rate is proportional to the square of adsorption driving force. The adsorption of strontium ions by special geological cement is monolayer adsorption.
Problems and Management Countermeasures for Radiation Safety in Scrap Metal Recycling in Guangxi
Chang Sheng, Li Lihong, Li Kai
RADIATION PROTECTION BULLETIN. 2017, 37(2): 22-25.
Abstract
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21
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Recycling of scrap metal can effectively improve resource utilization and protect the environment. However, due to theexistence of some management problems, a few radioactive sources used in the field of nuclear technology application, or some radioactive contaminated metals also enter the scrap metal recycling sector, through recycled metal products intothe community, threatening public health and environmental safety. The specialinspection work of radiation safety in scrap metal recycling in Guangxi in 2016is introduced. The present situation and existing problems in this regard is analyzed, and the countermeasures and suggestions are then put forward.
Advances in Radionuclide Strontium Adsorption
Lu Jiawei, Li Ning
RADIATION PROTECTION BULLETIN. 2017, 37(2): 26-29.
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20
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90
Sr is the most common pollution nuclide in the nuclear industry. Adsorption is an important method to treat
90
Sr pollution. In this paper, several commonly used methods for adsorption of
90
Sr, such as ion exchange, complexation / chelating adsorption, electrostatic adsorption, surface and porous adsorption, etc., is introduced, with their respective advantages and disadvantages compared. It is expectedto provide a reference for the process of treating radionuclides by adsorption.
Study on Safety Performance of Spent fuel DPCs
Jia Yijian, Sun Hongchao
RADIATION PROTECTION BULLETIN. 2017, 37(2): 30-34.
Abstract
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27
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As one kind of interim storage facility, spent fuel storage and transportation casks (DPCs) are an attractive option because of their flexibility and economical efficiency. DPCs need to be designedand verified, so that compliances with regulations for both transport and storage are achieved simultaneously. In this paper, some international experiences areintroduced, concerning DPCs' safety design and verification. It is expected toprovide references for spent fuel storage and transport safety in China.
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