Table of Content

20 March 2014 Volume 34 Issue 2

  

Investigation on Indoor Radon Levels in some Parts of China

Wang Chunhong, Pan Ziqiang, Liu Senlin, Yang Mingli, Shang Bing, Zhuo Weihai, Ren Tianshan, Xiao Detao, Yang Weigeng, Li Fusheng, Zhou Kaijian, Wu Jinhai, Xuan Zhiqiang, Tu Yu, Ge Liangquan

RADIATION PROTECTION. 2014, 34(2):  65-73. 

Abstract ( 8 )   PDF (801KB) ( 0 )  

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The paper reports the method and main results of investigation on radon in dwellings in some parts of China. Measurements of indoor radon concentrations were performed in one province and seven cities for one year, with every 3 months for one period, corresponding to spring, summer, autumn and winter seasons, using solid state nuclear track detectors. It involves 2 029 dwellings in total, and the population of the cities accounts for 12% of China. The investigation shows that the range of indoor radon concentrations is 5.3—183.0 Bq·m^-3, the average values with sample-weighted and population-weighted are (32.6±5.2) Bq·m^-3 and (30.7±4.3) Bq·m^-3 respectively. Radon concentrations in dwellings with different building ages, types and materials in urban and rural areas were compared in this paper, and seasonal variation of radon in dwellings were compared also.

Clearance of Slightly Radioactive Contaminats from NPPs

Guo Xiliang, Xu Chunyan, Feng Wendong, Gao Chao, Yang Weibing, Yue Zengqiang, Xiong Kouhong, Xiong Xiaowei, An Hongxiang

RADIATION PROTECTION. 2014, 34(2):  74-80. 

Abstract ( 5 )   PDF (1822KB) ( 0 )  

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Clearance of slightly radioactive contaminants is an effective way for the minimization management. Clearance process of slightly contaminants from NPPs was recommended according to related standard requirements and the characteristic of radwaste arising from NPPs.

Preliminary Study on Capturing and Encapsulating Radioactive Aerosol

Wu Mingliang, Zhang Wenjun, Tang Dezhong, Wang Xudong, Guo Lixiao, Wang Yongxian, Liu Haiqing

RADIATION PROTECTION. 2014, 34(2):  81-85. 

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The radioactive aerosol generated in decommissioning the reprocessing facilities should be treated for its high concentration. CaCO₃ powder was selected as the source to produce simulative aerosol in this study. The ultrasonic atomizing technology was applied to capture and encapsulate the aerosol. The experiment result shows that the concentration of simulative aerosol decreases with capture time; large particlesin aerosol can beeasily captured; when the capture liquid dose reduced to the certain value, the result of aerosol particle capturing and encapsulating became better evidently with the increase of dose. The experiment that carried out in a ²⁴¹Am contaminated glove-box proved the radioactive aerosol concentration could reduce from 183 Bq/m³ to 1.51 Bq/m³ after the capturing process. The radioactive concentration in the glove-box had no obvious change on the seventh day. Resuspension rate of the aerosol was 6.5% when opened the ventilation at the fourteenth day. The capture liquid had good encapsulating result for radioactive aerosol and loose contamination.

Influences of Improvement to Steam Generator’s Secondary Aerosol Deposition Model on BP Release Category

Huang Gaofeng

RADIATION PROTECTION. 2014, 34(2):  86-90. 

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Large frequency containment bypass (BP) accidents have big contributions to radiological consequences of a severe accident. MAAP4.0.4 is used to calculate source term of AP1000 BP release category, but it is incapable of accurate simulation for aerosol deposition in the complicated structure of secondary steam generator. With the basis of overseas experiments, aerosol deposition model is developed in this work, then the source code of MAAP4.0.4 is changed. Reassessment of BP release category is done, which indicates that, old model is conservative.

Theoretical Calculation of On-site Individual Dose for Xi’an Pulsed Reactor Nuclear Accident Emergency

Tang Xiuhuan, Yang Ning, Bao Lihong, Li Hua

RADIATION PROTECTION. 2014, 34(2):  91-96. 

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In order to rapidly assess individual dose of on-site nuclear accident emergency, a theoretical calculation method for Xi’an pulsed reactor nuclear accident emergency was established. Individual dose of response staff was calculated based on the characteristic parameter of XAPR and source items as input data. The results demonstrated that in case of design basis accident individual dose that operation and response staff received in reactor building is very limited, just about 1.78 mSv. In case of extreme hypothesis accident it was above 100 mSv considering 8 hours’ working, and dose that emergency environmental monitoring staff received was lower compared to dose inside building, it was 7.97×10^-6 and 9.95×10^-2 mSv at 35 m and 100 m boundary from the reactor site respectively. The results could be used as technological data of nuclear accident emergency, and the method could be applied in individual dose assessment of nuclear emergency in practice.

Criticality Safety Analysis to Transport Package of Intact AP1000 Fuel Assembly

Wang Xuexin, Zhuang Dajie, Cao Fangfang, Li Guoqiang, Xu Xiaoxiao, Sun Hongchao, Zhang Qun, Yan Feng

RADIATION PROTECTION. 2014, 34(2):  97-101. 

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Criticality safety needs to be considered carefully during the transport of intact nuclear fuel assemblies. Several factors should be taken in to account, such as package arrays, container damages under hypothetical accident condition and water moderation conditions. In this work, criticality safety analysis has been carried out for a Westinghouse XL shipping container loaded with AP1000 fuel assemblies. The fuel assembly and transport container have been modeled and simulated using the MCNP code. The results of MCNP show that the Westinghouse XL package is subcritical, if the number of packages meets the requirements in the approval of the competent authority.

Study of γ-ray Irradiation with Expressive Influence of IGF Related Genes in Human Hepatocytes

Li Jianguo, Yuan Hui, Yin Jingjing, Qin Xiujun, Zhang Wei, Wen Jianhua

RADIATION PROTECTION. 2014, 34(2):  102-108. 

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The study analyzed the effect-relationship of γ-ray irradiation with different doses (0.1, 0.2, 0.5, 1, 2 and 4 Gy) and different times(6, 12 and 24 h) of IGF related genes in human hepatocytes by real-time fluorescent quantitative PCR. The results indicated that insulin-like growth factor-1 receptor (IGF1R) showed low expression with different dosage and duration; insulin-like growth factor binding protein-1 (IGFBP1) showed high expression after radiation 6 h, 24 h showed low expression, 0.1 and 0.2 Gy showed high expression and 0.5, 1, 2 and 4 Gy low expression after radiation 12 h; IGF2BP3 showed low expression with 0.2 Gy and 6 h of 0.5 Gy, and high expression with other dosage and duration; IGFBP4 showed low expression with 6 h, and high expression with 12 and 24 h.

Development and Application of Radioactive Consequence Assessment System for Overseas Nuclear Accident

Li Bing, Chen Xiaoqiu, Qiao Qingdang, Yao Rentai, Hu Jiangkai, Xu Xiangjun

RADIATION PROTECTION. 2014, 34(2):  109-117. 

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Regional meteorological numerical prediction and consequences evaluation for long-range transportation of radioactive contaminants are integrated into Radioactive Consequence Assessment System for Overseas Nuclear Accident (RADCON), which is used to simulate radioactive release from any point within the globe. The structure and function of RADCON is described, as well as an application analysis by assuming the Fukushima Daiichi Nuclear Power Plant nuclear accident. Results show that RADCON can truly reflect the spatial and temporal distribution of radionuclides released into the environment and provide technical support for emergency decision.

Jiangsu Province’s Indoor Radon Levels and Public Dose Evaluation

Wu Xiaoping, Zhang Qihong, Xiao Yongjun, Qiu Xiaoping, Zhang Bin, Wu Yuli

RADIATION PROTECTION. 2014, 34(2):  118-123. 

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With CR-39 SSNTD, nearly 900 indoor radon concentration levels of 13 provincial administered cities in Jiangsu province were investigated. The results show that the highest level of indoor radon concentration in Jiangsu is 238 Bq/m³, the lowest level is 5 Bq/m³, the arithmetic mean value is 30 Bq/m³, the population weighted arithmetic average value is 29.7 Bq/m³, the geometric mean value is 28.2 Bq/m³, and the public annual average effective dose induced by indoor radon is 0.76 mSv. Through the analysis of correlation coefficients between indoor/outdoor radon concentration and ²²⁶Ra content in soil, it can be preliminary concluded that the main factor influencing the indoor radon concentration in Jiangsu province is the radon exhalation of geological construction foundation (soil and rock).

Tracing Management of Radioactive Solid Waste at SMNPP

Ma Pengxun, Liu Huichun, Jin Hairui, Liu Zhiyuan

RADIATION PROTECTION. 2014, 34(2):  124-128. 

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Radwaste management is one of the important management activities of nuclear power plant. SMNPP implements entire tracking to radioactive solid waste from generation to treatment, conditioning and storage at last. For this purpose, the radwaste management system SMNPP developed can figure out and track the radwaste not only by category, statistical period, reactor unit, but also by the specific sources of waste (e.g. operation or process system), and ultimately can provide basic information for radioactive solid waste management and making targeted waste minimization measures.