Table of Content

20 July 2015 Volume 35 Issue 4

  

Investigation of nuclear power plant postulated siting accident

Zhang Lin, Chen Xiaoqiu, Li Bing

RADIATION PROTECTION. 2015, 35(4):  193-198. 

Abstract ( 5 )   PDF (1109KB) ( 0 )  

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The evolutionary history and researching progress of nuclear power plant postulated siting accident of the U.S. nuclear regulatory authority is introduced. A set of assumptions of postulated siting accident is recommended for determining the exclusion area boundary (EAB) of nuclear power plant.The calculated maximum radius of the exclusion area about the M310 and AP1000 nuclear power plant is provided. The results indicate that: (1) The maximum distance of EAB is no more than 1.4 km and 1.9 km; (2) During siting phase, application of the postulated siting accident to determine the boundary of nuclear power plant, without considering the removal capability of active engineered safety feature, is practicable.

Criticality safety analysis for cask washdown pit stored new fuel assemblies of Sanmen NPP unit 1

Li Xuesong, Ma Pengxun

RADIATION PROTECTION. 2015, 35(4):  199-203. 

Abstract ( 6 )   PDF (1210KB) ( 0 )  

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Criticality safety is a major concern for nuclear safety in new fuel storage. Double contingency accident of new fuel criticality safety analysis must be considered for new fuel storage. SCALE was used for the criticality analysis of new fuel stored in cask washdown pit in Sanmen Nuclear Power Plant in this paper. The results show that plans for new fuel storage in cask washdown pit in Sanmen Nuclear Power Plant are safe even when two independent abnormal events occur simultaneously.

Shielding performance measurement and assessment for FCTC10 industrial cobalt-60 transport container

Li Guoqiang, Zhuang Dajie, Sun Hongchao, Luo Xiaowei, Yang Zhe, Wang Pan

RADIATION PROTECTION. 2015, 35(4):  204-208. 

Abstract ( 6 )   PDF (1429KB) ( 0 )  

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FCTC10 container is designed to transport cobalt-60 radioactive sources used in irradiation industry. It belongs to type B (U) grade Ⅲ (yellow) package when being loaded with a cobalt-60 source of 180 thousands curie. The container is constituted by shielding container, basket, protective cover, and bracket. Shielding ability is provided mainly by stainless steel shells, tungsten alloy and lead among steel shells. Radiation level around the container with maximum load are given through both Monte Carlo method simulation calculation and experiment measurement. It is proven that the shielding performance of the container is complied with the requirements in GB 11806—2004. Exposure doses of workers and public key groups are given based on hypothetical exposure scene according to transport practice experience. The results show that exposure doses of the workers and the public are less than the constraint dose considered in design, and also lower than dose limit regulated in GB 18871—2002. The dose received by the responders will be small becouse the increase of radiation level outside the container is tess than one time under design basis accidents.

Dose-effect relationship between premature chromosome fragment and low dose X-ray irradiation of different dose rate

Ma Ya, Liu Wei, Xin Yazhou, Hou Dianjun, Li Jieqing, Qiao Jianwei, Jia Ximing, Li Weiguo

RADIATION PROTECTION. 2015, 35(4):  209-213. 

Abstract ( 4 )   PDF (986KB) ( 0 )  

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There is a dose-rate effect between the chromosome aberrations and ionizing radiation in the low Linear Energy Transfer. To better estimate the biological dose absorbed under different dose rates, human peripheral blood was irradiated by X-rays in three different irradiation dose rates. CA was used to induce premature chromosome condensation, and then counted the chromosome fragments rate of the specimens by blind reading. To analyze the relationship between chromosome aberration rate and irradiation, we established the dose-response curves and mathematical model in different dose rates. Results show the aberration frequency increases with the absorbed dose when the dose rate is constant; and the aberration frequency increased with dose rate wthen the absorbed doses are the same. There is a notable dose-rate effect observed. Considering the dose-rate effect, approximate dose-rate dose-response curve should be chosen to estimate the absorbed dose in low linear energy transfer.

Protective effect of fullerene derivatives against mitochondria damage in rat liver induced by X-ray

Chen Qiping, He Jiaheng, Ma Zongping, Wang Ganquan, Liu Guoping

RADIATION PROTECTION. 2015, 35(4):  214-220. 

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To investigate whether fullerenes derivatives have protective effect to acute liver injury,we irradiated the Kunming mice with different doses of X-rays(12, 20, 40, 80 Gy),and injected fullerene derivative (CB) before or after irradiation. Experimental results show that the radiation can strongly induce free radical and damage to mitochondria, such as: to swell mitochondria, to produce lipid peroxidation and malondialdehyde (MDA). Chelating agent can significantly reduce the swelling of mitochondria and the formation of MDA, so as to maintain the structure integrity and function of mitochondria.

Application of GMS in the numerical simulation of nuclides migration in groundwater for nuclear power plant

Liu Yong, Mao Yawei, Zheng Wei, Bai Xiaoping

RADIATION PROTECTION. 2015, 35(4):  221-226. 

Abstract ( 6 )   PDF (2497KB) ( 0 )  

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Environmental impact assessment of groundwater for nuclear power plant has been a focus after the Fukushima accident. TA three-dimensional numerical simulation to the groundwater at an inland nuclear power plant site was carried out using GMS. Prediction and assessment were then made to the migration mode and influence scope of key radionuclides including H-3, Cs-137, and Sr-90. Results show that H-3 with a relatively fast speed might have an effect on the site, but would not contaminate the river in the north. However, Cs-137 and Sr-90 transported so slowly that they could merely migrate less than 100 meters, had no effect on off-site.

Study on radon absorption characterisitcs of structurally modified activated carbon

Wang Xiaowa, Wan Jun, Tu Yu

RADIATION PROTECTION. 2015, 35(4):  227-231. 

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Activated carbon is the main absorbent material in radon capturing. Studies on activated carbon radon capturing currently focus on ambient conditions, such as temperature, relative humidity, barometric pressure, radon concentration and the amount of absorbent. In order to analyze the influence of activated carbon molecular structure on radon absorption, oxidized activated carbon was prepared by oxidative activation of activated carbon. Experiments show differences in radon absorption between activated carbon and oxidized activated carbon. the relationship between adsorbents molecular structure and absorbability was analyzed.

Access monitoring system and upgrading for controlled area of multi-reactor NPPs

Wang Lifang, He Junnan

RADIATION PROTECTION. 2015, 35(4):  232-238. 

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This paper briefly introduces the controlled area access monitoring system (KZC) and its radiation protection management in multi-reactor nuclear power plant, in which the former KZC systems were operated separately in different reactor units. The related issues regarding to achieve one unified KZC management system are also discussed, such as personnel certification to controlled area, individual monitoring, radiation contamination monitoring and its control, etc. In order to manage two separate KZC systems of four reactor units as one in corporate monitoring system, a technical upgrade project of KZC systems was launched in Qinshan-II nuclear power plant. The problems occurred during the technical upgrading and their resolutions are presented in this paper.

Determination of ²¹⁰Po in atmospheric aerosol

Zhang Ye, Cao Zhonggang, Wang Kebin, Yu Danjiong

RADIATION PROTECTION. 2015, 35(4):  239-242. 

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The monitoring of ²¹⁰Po in aerosol is an important item for the environmental radiation protection. The alpha spectrum tracer method was employed in present work. In the sample treatment, the aerosol samples were first cut into pieces and mixed with standard ²⁰⁹Po as tracer then wet-digested by nitric acid, sulfuric acid, perchlorate acid system and extracted with 0.5 mol/L hydrochloric acid, finally auto deposited on silver in high temperature and high-speed stirring water bath. The developed method has been tested by several quality control systems, and widely used in atmospheric aerosol measurements of national controlled radiation monitoring points and in pollution source monitoring of uranium mine projects.

Design and commissioning of solid radioactive waste treatment system for CPR1000 Nuclear Power Plants

Lu Kefeng, Zhong Xiangbin, Li Chao, Zhang Peng, Lu Zhongcheng

RADIATION PROTECTION. 2015, 35(4):  243-247. 

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Solid radioactive waste treatment system is designed to collect and treat spent resins, concentrate, spent filter cartilages and other solid radioactive waste produced by CPR1000 units. The system consists of two subsystems, cementation and compaction, involving cementation, grouting, and super compaction processes. Radioactive waste resources, technological processes, system commissioning and performance of cemented waste forms are introduced in the paper, with special focus on difference analysis comparing with treatment system adopted in other NPPs. Suggestions on system improvement are briefed at last.

Review and analysis of industrial gamma-ray radiographic incidents from 2004 to 2013 in China

Peng Jianliang, Chen Dongliang, Jiang Wenhua, Li Xueqin, Zhou Xiaojian, Yu Tao

RADIATION PROTECTION. 2015, 35(4):  248-252. 

Abstract ( 6 )   PDF (1077KB) ( 0 )  

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To draw experience and lessons, preventing new occurrences, the industrial gamma-ray radiographic incidents had happened in recent ten years from 2004 to 2013 were summarized by analyzing their categories, levels, consequences and causes to provide technical reference in preforming similar practices in future. From 2004 to 2013, 17 industrial gamma ray detection accidents were listed in all with source lost or stolen incidents as the majority, three of which caused over exposure. 94% of the total 17 incidents belong to large or major incident, mainly attributed to human factors induced lack of safety measures. The utilization of Industrial gamma-ray radiography units should strictly abide by the Radiation Safety Requirements about the Gamma-ray Detection Device, and be imposed under stringent security supervision to foster safety culture preventing accidents.

Investigation of radiation environmental impact of uranium mining

Zhao Qiwen, Wang Guoquan

RADIATION PROTECTION. 2015, 35(4):  253-256. 

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This paper takes uranium mining and metallurgy decommissioning places of Yili area in Xinjiang as the object of study, the radiation environmental impact of these places were investigated, include Gamma absorbed dose rate, the radon exhalation rate, as well as the natural radionuclide concentrations in soil and water. It is showed that the pollution in a decommissioning place was grave, need urgent treatment.