Table of Content

20 November 2014 Volume 34 Issue 6

  

Applications of CORA Code on the Radiation Field Monitoring and Corrosion Products Control

Fu Yaru, Mei Qiliang, Pan Nan, Li Huaibin

RADIATION PROTECTION. 2014, 34(6):  337-342. 

Abstract ( 9 )   PDF (1017KB) ( 24 )  

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In order to develop deep research on corrosion products generation, distributions and control measures in China, the contents include corrosion products generation physical characteristic, principles of CORA code and code applicability, control measurements and radiation field research held by CORA code, and the collective dose analysis were introduced in this article. Moreover some conclusions and suggestions were introduced in this article:1, CORA code is applicable as well when the design condition changes; 2, CORA code is a popular worldwide method to analyze the plant radiation field and corrosion products control measurement; 3, the measurements of controlling the Co concentration in the U-tubes in SGs, increasing the LiOH concentration in the reactor coolant are effective for the corrosion products control. In addition, CORA code is strongly recommended for the plant radiation field and corrosion products control analysis.

Preliminarily Study on Applicability of UF₆ Leakage Accident Assessment by Shallow Model

Chen Hailong, Dong Yuyang, Liu Yafang, Zhao Yangjun, Gu Zhijie

RADIATION PROTECTION. 2014, 34(6):  343-348. 

Abstract ( 14 )   PDF (876KB) ( 25 )  

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The purpose of this article is to use SLAB model and HGSYSTEM/UF₆ model, to build the near source field evaluation model after UF₆ leakage accidents. And based on the data of three UF₆ release experiments carried by the French Bordeaux National Experimental Base, it tested the model preliminarily. It turned out that the model can simulate atmospheric diffusion and migration in the near source field after UF₆ leakage very well (P/O=1.0—2.4), the simulation results errors are acceptable.It also aims to provide theory basis for the later large model program development, and offer help for more precision simulation of contaminants transfer after UF₆ leakage accidents.

Feasibility Study on ANSYS Simulation for Temperature Filed in High-level Radioactive Waste Repository

Wan Lei¹, Jia Meilan¹, Zhang Chunhui², Sun Qinghong¹, Liu Wei¹, Yang Zhongtian¹, Zhao Shuaiwei¹, Li Honghui¹, Liu Jianqin¹

RADIATION PROTECTION. 2014, 34(6):  349-355. 

Abstract ( 12 )   PDF (3120KB) ( 28 )  

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To demonstrate the feasibility and accuracy of the ANSYS software for temperature field prediction in High-level radioactive waste (HLW) repository, ANSYS workbench is used as a platform for 2D model and 3D model simulation based on the self-designed thermal effect device and its corresponding experimental parameters. The results show that the simulation data has a high goodness of fit to the experimental data. The average of the relative difference between simulation data and experiment data for the three concerned sensors are 0.68%, 0.60% and 0.50%, respectively, during the heating stage, while the average of relative difference is 1.34% during the balance stage. It is indicated that the ANSYS thermal analysis is feasible for temperature field prediction of the disposal unit in HLW repository.

Distribution of Automatic Monitoring Sites in National Atmospheric Radiation Environmental Monitoring Network

Zeng Zhi¹, Zhang Li¹, Ma Yongfu², Liang Meiyan², Zhao Shunping², Li Junli¹, Cheng Jianping¹

RADIATION PROTECTION. 2014, 34(6):  356-360. 

Abstract ( 10 )   PDF (1435KB) ( 27 )  

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Based on analyses to the nationwide wind direction field, wind speed field and the population distribution, a site distribution method of the nationwide radiation environmental monitoring network was proposed, which includes monitoring sites distribution density and major distribution routes, and etc. Combining with the distribution of nuclear facilities, location arrangements of the sites in the overall nationwide layout was set forth, including annular distribution, special route distribution, nuclear power plant alpine defense distribution and radiological research institutes radial distribution. The distribution of automatic monitoring sites should be relatively dense in Shanxi, Sichuan, Yunnan, Guizhou, Hunan, Guangxi, Guangdong, Fujian, and Zhejiang province; and loose in Tibet, Xinjiang, Inner Mongolia, and Qinghai. With this site distribution method, the radiation environmental condition can be effectively monitored.

Effects of RAN Gene Silencing by siRNA on Apoptosis and Cell Cycle in Radiation Induced Genomic Instable Liver Cells

Dang Xuhong, ZuoYahui, Yuan Yayi, Liu Hongyan, Liu Jiangong, Zhang Ruifeng

RADIATION PROTECTION. 2014, 34(6):  361-365. 

Abstract ( 9 )   PDF (1359KB) ( 27 )  

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RNAi was used to inhibit RAN gene’s transcription and expression level of RAN. The apoptosis was detected by Annex in Ⅴ-APC flow cytometry (FCM) and the cell cycle was determined by FCM with single PI staining. Results of real time fluorescence quantitative PCR tests demonstrated that RAN gene can be inhibited efficiently by RNAi. The apoptosis percentage in RNAi group was lower than that in the negative control, the number of cells in G₁ phase were higher than in the negative control. These results indicated that RAN gene may maintain the genomic stability through regulating the cell apoptosis and cell cycles.

Optimization of Fluorescence X Ray Reference Radiation

Ding Yadong^1,2, Wei Kexin², Song Mingzhe², Liu Qiaofeng²

RADIATION PROTECTION. 2014, 34(6):  366-369. 

Abstract ( 9 )   PDF (1440KB) ( 26 )  

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In the reference radiation field of fluorescence X ray, intensity and purity of X ray are influenced by mechanical equipment, thickness of radiator, thickness of secondary filter, tube voltage of X ray machine. Based on the optimized structural design of reference radiation device, through theoretical analysis calculation and Monte Carlo simulation, differences of fluorescence intensity and purity following the thickness of radiator and secondary filter were obtained, and fluorescence intensity and purity influenced by X ray tube voltage were also got measured. The results show that: to the F-Cs radiation quality, when the thickness of radiator is greater than 490 μm, intensity is saturated. When the thickness of secondary filter equals to 327 μm, purity is the highest. Intensity increases with the rise of voltage, but purity declines with the increase of voltage.

Effect of Gamma-ray Irradiation and Thermal Aging on Adsorption Property of ¹³⁷Cs in Modified Sodium Bentonite

Zhao Shuaiwei, Li Honghui, Liu Wei, Liu Jianqin, Yang Zhongtian, An Hongxiang, Wan Lei

RADIATION PROTECTION. 2014, 34(6):  370-375. 

Abstract ( 8 )   PDF (1557KB) ( 27 )  

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With the modified sodium bentonite from Gaomiaozi, Inner Mogolia, as the object of study, the distribution coefficients of ¹³⁷Cs in its original form and froms of, being gamma-ray irradiated and gamma-ray irradiation-thermal sequential aging were measured separately using batch method. Results show that gamma-ray irradiation helps improve the ¹³⁷Cs absorbtion of the sodium bentonite under the experimental conditions in this study. Comparing with the modified sodium bentonite, the absorbtion of sodium bentonite experiencing gamma rays irradiation has an increment in the range of 30.1% to 39.4%. The results also show that compared with gamma rays irradiation, gamma rays irradiation-thermal sequential aging can make the absorption capacity of ¹³⁷Cs on modified sodium bentonite further intensified,mean increment reaches up to 16%.

Size Distribution Characteristics of Plutonium in Resuspended Aerosol at Contaminated Areas

Li Dongmei, Liu Longbo, Zhou Guoqing, Wang Xuhui, Jin Yuren

RADIATION PROTECTION. 2014, 34(6):  376-380. 

Abstract ( 10 )   PDF (1522KB) ( 23 )  

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Soil and fractioned aerosol samples were collected at some contaminated areas, and the ²³⁹Pucontent was determined. The size distribution characteristics of plutonium in the resuspended aerosol were analyzed. The results show that the average value of activity median aerodynamic diameter of plutonium is 3.1 μm under undisturbed conditions and increased to 12 μm under disturbed conditions. The typical size distribution patterns of plutonium are consistent with ¹³⁷Cs size distribution patterns proposed by other researchers. The enrichment factors were found to be 0.002—0.2 and showed no obvious relationship with diameters. Also, taking the mechanism of wind erosion of soil into consideration, the process of radionuclide resuspension is discussed.

Prototype Developemnt of a Portable Radionuclide Identification System

Liu Zhao, Chu Chengsheng, Hu Guangchun, Hao Fanhua, Zeng Jun, Ding Ge, Xiang Qingpei

RADIATION PROTECTION. 2014, 34(6):  381-385. 

Abstract ( 11 )   PDF (1709KB) ( 23 )  

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This paper presents the prototype of portable radionuclide identification system developed by the Institute of Nuclear Physics and Chemistry of China Academy of Engineering Physics. This portable radionuclide identification system which is a gamma ray spectrometer using a LaBr₃(Ce) detector and a pulse height multi-analyzer, can be applied in radionuclide detection, dosimetry, radioactive source searching and environmental radiation inspection. With this system, if any exceptional radioactivity was reported in the outflow from a nuclear power plant or nuclear material manufacturer, the type of radionuclides and the radioactivity as well can be identified and evaluated efficiently and precisely at the outflow securing the radiation safety to the operating staffs.

Design and Application on Impregnation and Drying Process of Nuclear-grade Activated Carbon in Vacuum Condition

Hou Jianrong, Shi Yingxia, Qiu Dangui, Xu Lutong, Qiao Taifei, Han Lihong, Li Yongguo, Kong Haixia

RADIATION PROTECTION. 2014, 34(6):  386-389. 

Abstract ( 9 )   PDF (1064KB) ( 26 )  

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The impregnating and drying technics in vacuum condition of nuclear-grade activated carbon were established based on our experimental results. In this paper, a large-scale process and its integrated equipment to produce impregnated activated carbon were designed via heat balance calculation. This equipment can produce impregnated activated carbon in a continuous impregnation and pre-drying mode with stable quality, high efficiency, short time, and no dust pollution in the process.

Discussion on Monitoring Items for Radionuclides in Influents from Nuclear Power Plants

Zhang Yanxia, Li Jin, Liu Jiacheng, Han Shanbiao, Yu Zhengwei

RADIATION PROTECTION. 2014, 34(6):  390-394. 

Abstract ( 10 )   PDF (1083KB) ( 27 )  

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For the radionuclide monitoring items of effluents from nuclear power plant, this paper compared and analyzed the IAEA general requirements, the routine monitoring items of radionuclide at China’s nuclear power plant and the experimental research results of low-level radionuclide in effluent. The necessary items and recommended items for the radionuclide monitoring of effluents from nuclear power plant were summarized then, which can provide references for the radioactivity monitoring activities of nuclear power plant effluent and the supervisions of regulatory departments.

Quality Control for Personal Monitoring by Thermoluminescence Dosimeter at Tianwan NPP

Huang Rong, Zhao Honghe, Wang Yongjun, Hou Bingjun

RADIATION PROTECTION. 2014, 34(6):  395-399. 

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This article mainly describes the specific methods and measures of quality control taken when individual exposure dose is monitored by TLD system at Tianwan NPP. Through a series of control measures during measurement, calibration and maintenance, the quality of the individual dose monitoring in TNPS has been improved.

A Discussion at Performance of Several Filter-type Discriminating Thermoluminescence Personal Dosimeters

Qin Yongchun, Yang Xiaoyong, Chen Wei, Shi Xiaodong, Wang Furu, Yu Ningle, Wang Jin

RADIATION PROTECTION. 2014, 34(6):  400-403. 

Abstract ( 12 )   PDF (1863KB) ( 26 )  

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Discriminating TLDs (thermoluminescence personal dosimeters) are capabale of energy identification in personal dose monitoring. Energy responses, energy identifying curves, dose responses of three filter-type discriminating TLDs were experimented. Results show that there are differences and similarities among the TLDs being experimented, which can all play a role to certain extent in energy identifying.

Investigation Report on French Vitrification Technology

Liu Weiping, Gao Zhen, Fang Chengrong, Ji Toujie, Song Yuqian

RADIATION PROTECTION. 2014, 34(6):  404-406. 

Abstract ( 13 )   PDF (1026KB) ( 0 )  

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This article introduces the French vitrification technology. The application progress of French rotary calciner furnace+hot/cold crucible technology and vitrification facilities operating conditions are elaborated, with emphasis on questions of domestic experts’ concerned, which provides theoretical support for comparison and selection of technology roadmap for HLLW treatment in 404 company.