Table of Content

20 June 2014 Volume 34 Issue 3

  

Progresses

Groundwater Monitoring Strategy for Nuclear Power Station of American Nuclear Regulatory Commission and Its Implications

Qin Chunli, Xu Yueping, Chen Chaofeng, Shanguan Zhihong

RADIATION PROTECTION BULLETIN. 2014, 34(3):  1-5. 

Abstract ( 23 )   PDF (381KB) ( 78 )  

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In this paper, NRC's groundwater monitoring strategy for nuclear power station is summarized. This strategy combines model development with site monitoring and has been well validated, Meanwhile, current situation of groundwater monitoring at nuclear power station in our country is schematically reported in order to provide references to establish and perfect groundwater monitoring at China's nuclear power stations.

Articles

Monitoring Results of Radiation Environmental Quality in Zhejiang Province during the Eleventh Five-year

Xu Hong, He Bisheng, Hu Xiaoyan, Song Lujun, Ding Jinlin

RADIATION PROTECTION BULLETIN. 2014, 34(3):  6-11. 

Abstract ( 28 )   PDF (241KB) ( 24 )  

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In order to master the radiation environmental quality situation and its development trend in Zhejiang Province timely and entirely, the systematic radiation environmental quality monitoring was launched during the Eleventh Five-Year. Themonitoring content covers air, soil, drinking water and surface water of "EightDrainage". The monitoring results showed that the gamma radiation dose rate onthe field, the natural radionuclide activity concentration in soil and environmental freshwater (drinking water, lake water) were at the same levels as the value of national natural background investigation in 1985. The results indicated that radiation environmental quality in Zhejiang Province was within the normal limits during the Eleventh Five-Year.

Effects of Mild Hypothermia on Acute Radiation Syndrome in Mice

Li Shufang, Yue Juan, Huang Liqun, Wang Yongli, An Quan, Li Youchen, Zhou Jinyuan

RADIATION PROTECTION BULLETIN. 2014, 34(3):  12-15. 

Abstract ( 24 )   PDF (125KB) ( 29 )  

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This paper is to investigate the effect of mild hypothermia on acute radiation syndrome in mice. Forty male BALB/c mice were randomly are divided into 4 groups. The mice were exposed to gamma ray at6.0 Gy,0.92 Gy/min, the mice in mild hypothermia+radiation group were receivedmild hypothermia treatment before irradiation and radiation+mild hypothermia group after irradiation. The descend range of pripheral blood leukocyte number in mild hypothermia+radiation group was 1 week in advance to restore; Thymus weightand coefficient increased, the ratio of PCE/(PCE+NCE) was lower than radiation group.The descend range of pripheral blood leukocyte number in radiation+mild hypothermia group was lower than radiation group on the first day after irradiation, and 4 days in advance to restore. The descend range of pripheral blood leukocyte number in mice treated by mild hypothermia either before or after irradiationdecreased lower in early time after irradiation and recovery earlier, Mild hypothermia had some protective effect on mice radiated at 6 Gy.

Calculation of Dose Rate Conversion Coefficients for External Exposure to Photon emitters in Soil Based on EGS Monte Carlo Code

Hua Zhengdong, Hong Yun, Sui Guangkai, Dai Jiwei

RADIATION PROTECTION BULLETIN. 2014, 34(3):  16-19. 

Abstract ( 26 )   PDF (221KB) ( 63 )  

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The conversion coefficients of photondose rate above ground from photon emitters in soil were calculated using the EGS Monte Carlo code. Calculations were performed for 16 photon energies from 50 keV to 3 MeV and for 30 plane radius from 5 cm to 200 m. The conversion of photondose rate above ground from specific activity of nuclides form ²³⁸U decay chain, ²³²Th decay chain and ⁴⁰K in soil were also given. The comparison between these results and the data deduced previously by otherauthors indicates a good agreement, less than 10% difference.

Management

Nuclear Safety Goals and Public Acceptance

Li Chaojun, Zhang Chunming, Zuo Jiaxu, Chen Yan, Fu Zhiwei, Song Wei

RADIATION PROTECTION BULLETIN. 2014, 34(3):  20-23. 

Abstract ( 35 )   PDF (342KB) ( 118 )  

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After Fukushima accident, the international society pays more attention on the safety of nuclear power. Nuclear safetygoals have very important impact on the nuclear safety as the criteria of nuclear power plant safety assessment. Public acceptance has important effect on thenuclear power development. Presently, how to improve the safety of the plant andmake the public have a better understanding of safety goals is one of the mainproblems to most of countries in the process of nuclear power expansion. This paper introduces the development of safety goals and the public acceptance of nuclear power expansion, and discusses how the public acceptance impact on setting nuclear safety goals and nuclear power expansion. Finally several helpful suggestions are made on how to change public acceptance of nuclear power.

Experiences

Debug Method of Sealed Gas Detector C2 Gate at Nuclear Power Plants

Li Xiang, Yu Zhe, Li Mailin, Wang Jianxin, Ren Yi, Zhang Jia, Liu Jinjin, Liu Yun

RADIATION PROTECTION BULLETIN. 2014, 34(3):  24-27. 

Abstract ( 30 )   PDF (276KB) ( 30 )  

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A description is presented of the debug method of C2 gate at nuclear power plants using sealed gas proportional counter as detector, including the analysis of the feasibility and necessity of performance optimization. To ensure the optimized detection efficiency, the high voltage value is to be determined. The lowest detectable limit of the equipment is calculated and the low background alarm threshold is set. Protective method for detector are provided.

Comparison of Environmental Gamma Radiation Dose Rates in Zhejiang Province in 2012

He Bisheng, Ding Xun, Shang Jiangfeng, Liu Gongye, Xu Hong

RADIATION PROTECTION BULLETIN. 2014, 34(3):  28-31. 

Abstract ( 22 )   PDF (171KB) ( 28 )  

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A comparison of environmental radiation dose rate in Zhejiang province was performed by Zhejiang Radiation Environmental Monitoring Station in 2012 in order to evaluate the quality of radiation environmental monitoring. The robust statistical Z score method was taken to evaluate the consistency of measuring results in this work. The monitoring resultsfrom 20 instruments at 5 comparison points showed that outlier, questionable value and satisfactory value was 5%, 6% and 89% of the total, respectively. We found the problems of instruments through this comparison to ensure the accuracy ofmonitoring results.

Corrosion Analysis of Quench Tower for Radioactive Incinerator

Yang Lili, Li Xiaohai, Zheng Bowen

RADIATION PROTECTION BULLETIN. 2014, 34(3):  32-35. 

Abstract ( 20 )   PDF (157KB) ( 22 )  

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The reason why a quench tower for radioactive waste incinerator was eroded seriously during the long term operation was analyzed, aiming at presenting anti-corrosion measures in aspects of materialselection, medium condition and management, which is useful for us to improve the corrosion of equipment.

PrimaryExperimental on Concentrate Drying in Electrically Heated Drum

Yan Xiaojun, Liu Zhaofeng, Li Honghui, Liang Dong, Gao Chao, Jia Meilan

RADIATION PROTECTION BULLETIN. 2014, 34(3):  36-38. 

Abstract ( 21 )   PDF (356KB) ( 24 )  

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In order to minimize the wastes, we have done the in-drum drying technology research on the concentrated solution. The results show that the volume reduction ratio of the concentrated solution is about 4. At the same time the average water content is less than 15%. All of themprove that the electric heater drying technology is feasible.

Reports

Personal Dose Monitoring of Radiation Workers from 2001 to 2006 in Xinxiang

Zhang Bingjie, Liu Tongzhen, Ding Weimin, Jia Tianhe, Wang Jianwei, Mao Yuxuan

RADIATION PROTECTION BULLETIN. 2014, 34(3):  39-42. 

Abstract ( 22 )   PDF (104KB) ( 25 )  

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The personal dose monitoring results of radiation workers from 2001 to 2006 in Xinxiang city are presented. The resultshows that the annual effective doses ranges 0.04-3.95 mSv for nuclear medicalworkers, 0.04-4.13 mSv for radiotherapy workers, 0.13-1.48 mSv for industrialradioisotope workers. These three kinds of work conditions are safe. 0.04-9.35mSv for medical diagnostic X-ray workers, 0.16-15.72 mSv for industrial radiography workers, 0.04-34.82 mSv for interventional radiology workers, 5-20 mSvfor some staff, >20 mSv for tow interventional radiology workers, respectively.