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Table of Content

    20 February 2015 Volume 35 Issue 1
      
    Management of Radiation Protection during Overhaul at CPR1000 PWR
    Yang Yan, Yang Xiaoqiang, Guo Fei, Zuo Guoyong, Dong Zhengpeng, Deng Kechun
    RADIATION PROTECTION BULLETIN. 2015, 35(1):  1-5. 
    Abstract ( 20 )   PDF (409KB) ( 47 )  
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    Specialized overhaul is practiced at CPR1000 PWR, facing new opportunity and challenge in radiation protection management. This paper presents a description of the radiation protection management during first overall of N101 at Ningde Nuclear Power Plant and provides a comparison with Daya Bay NPP which has the similar reactor type, with differences between both being pointed out and relevant improvement suggested.
    Water Chemistry Monitoring and Control in the Reactor Shutdown Process with Fuel Cladding Failure
    Wu Huaqiang, Chen Zhanggui, Liu Hui, Liu Heng, Zhan Xiaocong, DengJun
    RADIATION PROTECTION BULLETIN. 2015, 35(1):  6-9. 
    Abstract ( 17 )   PDF (339KB) ( 9 )  
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    The water chemistry monitoring and control during the reactor shutdown process with fuel cladding failure is very important for nuclear safety, source term and personnel dose reduction, and the economic benefit improvement for refueling outages. This paper describes water chemistry monitoring and control method during the reactor shutdown process. By analyzing the practice effect of the water chemistry control during the first reactorshutdown process with fuel cladding failure in Ningde NPP, and investigating the abnormal conditions encountered, we proposed a solution.
    Radiation Protection in Wedge Valve Repair at a PWR Nuclear Power Plant
    Zuo Guoyong, Wang Yonghui, Pu Lixing, Yang Yan
    RADIATION PROTECTION BULLETIN. 2015, 35(1):  10-14. 
    Abstract ( 21 )   PDF (114KB) ( 103 )  
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    This article describes the radiation risks from wedge valve maintenance in the context of variable conditions. Sepcific protection measures are proposed based on ALARA principle.
    Source Term Analysis for PWR Primary Coolant Leakage in the Case of Fuel Element Rupture
    Li Jianlong, Zhang Wenfa, Xu Xianda, Wu Guodong, Ha Hanzhang
    RADIATION PROTECTION BULLETIN. 2015, 35(1):  15-18. 
    Abstract ( 16 )   PDF (520KB) ( 44 )  
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    The source term of airborne radiationinside reactor building for PWR primary coolant leakage in the event of fuel element rupture is discussed. And two methods of calculation of noble gas content in the regard are introduced.
    Calculation of Radioactive Noble Gas Content Inside RPV in PWRs
    Li Jianlong, Tan Linglong, Chen Wentao, Yang Jian, Ha Hanzhang
    RADIATION PROTECTION BULLETIN. 2015, 35(1):  19-23. 
    Abstract ( 16 )   PDF (1249KB) ( 15 )  
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    Radioactive noble gases are occurringin the process of PWR NPP operation. The study of them is of significance to thesafety of NPP. A calculation method of noble gas content inside RPV is introduced, based on an event of radioactive gas leakage during outage of a PWR NPP.
    Trend Forcasting of Radioactive Level inside Reactor Containment
    Sun Wei, Chen Ligang, Li Fuping, Liu Gang
    RADIATION PROTECTION BULLETIN. 2015, 35(1):  24-27. 
    Abstract ( 17 )   PDF (463KB) ( 11 )  
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    The trend of inert gas radioactivity level inside NPP containment was forecasted, using operating data in normal and abnormal working conditions (or accident). It was then validated with online monitoring data. This provides an important anticipation to the safe and stable operation of the nuclear power. When an abnormal event or accident happens, the response decision can be taken with the forecast data used. In this paper, combinedthe actual operation data of NPP, a prediction method of inert gas radioactivitylevel inside the containment is briefly summarized.
    Proportional relationship analysis of 85Kr and 133Xe in the gaseous effluent on normal operating conditions of nuclear power plant
    Li Fuping, Liu Hui, Liu Heng, Zhang Yang, Cheng Ligang, Sun Wei
    RADIATION PROTECTION BULLETIN. 2015, 35(1):  28-32. 
    Abstract ( 36 )   PDF (196KB) ( 10 )  
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    The inert gas monitoring results are generally lower than the detection limit onnormal operating conditions, if relevant monitoring results lower than the detection limit, half of its emissions by statistical detection limit may overestimated the annual emissions. By determining activity proportional relationship of85Kr and 133Xe, when the 85Kr of maximumhalf-lifein the inert gas source term was less than the detection limit, its activity concentration can estimate indirectly. Thus the annual emissions statistics of 85Kr can obtained more objectively.
    Power Performance Testing of Nuclear Grade Resin under Boron Saturation
    Yan Weilong, Hu Xiangmeng
    RADIATION PROTECTION BULLETIN. 2015, 35(1):  33-34. 
    Abstract ( 19 )   PDF (322KB) ( 9 )  
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    This study deals with the saturation and adsorption of boric acid onto nuclear grade lithium resin , the effect of temperature on saturability resulting from saturated resin boron, and boron releaseat different concentrations of boric acid. The results have shown that that theboric acid onto resin is a longer process; resin tends to be saturated when boric solution reaches elevenfold volume of resin; a certain degree of boron release appears when water flow temperature rises; a new equilibrium is reached when effluent reaches sixfold volume of resin.
    Chemical Method-based Hydrogen Removal at Ningde Nuclear Power Plant
    Deng Jun, Liu Heng, Wu Huaqiang, Yang Shunlong, Bai Zhaotao
    RADIATION PROTECTION BULLETIN. 2015, 35(1):  35-37. 
    Abstract ( 13 )   PDF (141KB) ( 12 )  
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    Chemical method to, by addition of H2O2, remove hydrogen dissolved in the water was discussed for its practicalityat PWR plant. The successful application of this method in the Ningde nuclear power plant was summarized in the paper. It has been shown to be able to improvethe efficiency of unit shutdown and optimize unit shutdown mode, suitable for dissolved hydrogen removal at PWR nuclear power plant.
    Application of Online Conductivity and Dissolved Oxygen Monitoring Devices in Ningde NPP
    Liang Yicai
    RADIATION PROTECTION BULLETIN. 2015, 35(1):  38-40. 
    Abstract ( 19 )   PDF (135KB) ( 23 )  
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    Reactor boron and water supply systemis an important component of the primary circuit auxiliary system in PWR NPPs. Online monitoring devices for total conductivity and dissolved oxygen were introduced into the sampling system of Ningde NPP, to perform exact and real-time water quality monitoring in the tank REA001/002. The operation results show favourable effects. Such devices are worth promotion in other similar NPPs.
    Emergency Monitoring of HAB Prorocentrum Donghaiense
    Wang Hongbo, Li Fuping, Sun Wei, Li Jing, Liu Gang
    RADIATION PROTECTION BULLETIN. 2015, 35(1):  41-44. 
    Abstract ( 14 )   PDF (161KB) ( 19 )  
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    Harmful algae blooms (HAB) threaten the safety of cooling system of coastal power plants. With a timely and effectivemonitoring of HAB, there will be enough time to carry out emergency preparation.It is of practical significance for the safe operation of the unit. This paperbriefly introduces the process of emergency monitoring of HAB Prorocentrum Donghaiense in Qingchuan Bay. Based on analysis and comparison,the key parameters for HAB are determined to be turbidity, chlorophyll concentration, concentration ofblue green algae. This provides support for early warning and emergency monitoring of HAB.