最新刊期
      卷 0 ， 期 0 ， 2020
      • ZHENG Mingguang1 YE Cheng2 HAN Xu2 1
        Vol. 33, Issue 2, (2010)
        摘要：In this paper,we discuss the world’s recent development of nuclear power,which does not seem to achieve what has been anticipated by the groups of experts.In this regard,there is before us a heavy responsibility and a long way to go.Nuclear power is very important for China’s environmental protection and economic development.Suggestions are made for longer-term demand for the electricity and long-term nuclear power plan in China.According to the nuclear power strategy adopted by developed nations,we believe that China’s nuclear power strategy and nuclear techniques shall be based on advanced PWR,such as AP1000,CAP1000,CAP1400 and CAP1700,which will be the main NPP types in a long time in China,and the latter two shall be highly competitive in the world.For generation IV reactors,the SCWR (Supercritical Water Reactor) is more suitable than others,in terms of the industrial development in PWRs and fossil fuel super critical generator systems in China.In addition,investment should be increased in fast reactors to achieve the fuel closed-cycle,and attentions should be paid to the TWR (Traveling-wave Reactor),and small and medium-sized reactor as well.Finally,conclusions are given for large scale development of nuclear power in China.  
        关键词：New energy;Nuclear power;Long-term plan;Generation IV;TWR;CAP1400;CAP1700   
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        发布时间：2021-03-05
      • YAN Jinquan ZHANG Qinfang QIU Yongping ZHOU Quanfu QIU Zhongming CHEN Song
        Vol. 33, Issue 2, (2010)
        摘要：The software for Level 1,2 and 3 probabilistic safety assessments (PSA) was developed based on the PSA code by the US Nuclear Regulatory Commission and independent research.It was applied to integrating the design of a 300 MW nuclear power plant,unit 2 (C-2).It includes the analysis of initiating events,event trees,fault trees,dependency analysis,human reliability analysis,database analysis,event sequence quantification,plant damage state analysis,accident progression and containment response analysis,source term analysis,large early release frequency (LERF) analysis,uncertainty analysis,importance/sensitivity analysis,applications during design phase,etc.The model of Level 1 and 2 PSA was established for the C-2 unit.Several design improvements based on the PSA were implemented in the design,such as the isolation valves on the mini-flow line of the safety injection pump and spray pump,reciprocating charging pump in chemical and volume control system,essential service water system,etc.The unit’s internal events at power generation were assessed as 7.25×10-6/ry for core damage frequency (CDF) and 3.24×10-7/ry for LERF.The C-2 PSA has not only justified the balance of its design,but also provided the probability assessment information for optimizing C-2 design and operation strategies,reducing the risk of severe accidents efficiently.  
        关键词：PSA;Event tree;Fault tree;Severe accident;Design improvement   
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        发布时间：2021-03-05
      • YANG Ping ZHOU Quanfu CHEN Song WANG Zhe FANG Likai LIU Xin HU Chengxiang ZHENG Yaoyao KE Xiao ZHAN Wenhui
        Vol. 33, Issue 2, (2010)
        摘要：In this paper,we report our achievements in the project of verification and optimization for Qinshan NPP EOP.Based on principal results of the research on design features and parameters of the nuclear power plant,a total of 22 steps and key parameters of the Qinshan NPP EOP have been verified and 12 optimizations have been suggested.  
        关键词：EOP;ERG;Verification;Optimization   
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        发布时间：2021-03-05
      • ZHAN Wenhui
        Vol. 33, Issue 2, (2010)
        摘要：The Steam Generator Tube Rupture (SGTR) accident has been analyzed with RELAP5/MOD3 thermal hydraulic system analysis code under the conditions that the safety valve of affected SG is stuck open.The AFW is unavailable,and only one HPSI pump is available.It can be mitigated successfully if the operators take actions to cooldown and depressurize RCS within 150 min after the safety injection signal.The results show that the active core is covered by coolant before the break flow is terminated with the balance between primary and secondary side of affected SG at atmospheric pressure.  
        关键词：SGTR;RELAP5/MOD3 code;Cooldown and depressurization;Stuck open   
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        发布时间：2021-03-05
      • LIU Haibin LI Zhaohua ZHANG Minjun
        Vol. 33, Issue 2, (2010)
        摘要：The probabilistic safety assessment (PSA) model of the third generation nuclear power technology (AP1000) is built with CAFTA code,while the RiskSpectrum code is used in our institute.Based on the analysis of the data files of the two codes,the conversion code CAFTA2RS is developed to extract information from the PSA model built with CAFTA,modify the data format that incompatible with RiskSpectrum,convert the gate type,such as AANB,EQU and so on,to the gate type acceptable with RS,and finally convert the PSA model from the format of CAFTA code to the format of RiskSpectrum code automatically.  
        关键词：AP1000;CAFTA;RiskSpectrum;Model conversion   
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        发布时间：2021-03-05
      • ZHU Libing YANG Bo MEI Qiliang YANG Ping LIU Xin
        Vol. 33, Issue 2, (2010)
        摘要：The reactor core design,mechanical design of cobalt adjuster rod assembly and safety analysis have been performed after the 21 stainless steel adjuster rod assemblies were replaced by cobalt adjuster rod assemblies in the reactivity control system of CANDU-6 reactor.The analysis results show that the grouping,distribution in reactor,and operation mode of the cobalt adjuster rod assemblies are the same as the stainless steel adjuster rod assemblies.During the operation of the cobalt adjuster rod assemblies for producing 60Co,the reactor core nuclear property,the reactor safety operation,and the radioprotection safety can be preserved.  
        关键词：Stainless steel adjuster rod assemblies;Cobalt adjuster rod assemblies;Reactor core nuclear design;Mechanical design;Safety analysis;Radioprotection safety   
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        发布时间：2021-03-05
      • LIU Jiazheng
        Vol. 33, Issue 2, (2010)
        摘要：The steady and transient performance analysis for the fuel rods in FA300-4 fuel assembly with M5 alloy cladding has been performed.Performances of the fuel rods have been analyzed,including temperature of the fuel and cladding,and stress and strain,inner pressure and corrosion of the cladding,etc.In order to do the analysis,the performance analysis code (FEMAXI-IVM) has been modified.The results show that analysis for fuel rods of FA300-4 fuel assembly with M5 alloy cladding can be conducted under steady and transient conditions,so the integrality of the fuel rods and safety of the reactor are ensured.  
        关键词：Fuel rod;Steady;Transient;Safety analysis   
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        发布时间：2021-03-05
      • DING Jie ZHU Libing
        Vol. 33, Issue 2, (2010)
        摘要：In this paper,the process of 3-D modeling and motion simulation of fuel rod-replacing equipment using SolidWorks is described,and the application of SolidWorks in manufacturing and design improvement is discussed.Complexity of the manufacturing is reduced and reliability of the design is improved.  
        关键词：Fuel rod-replacing equipment;3-D modeling;Motion simulation;SolidWorks   
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        发布时间：2021-03-05
      • ZHOU Qin DING Jie
        Vol. 33, Issue 2, (2010)
        摘要：In this work,3-D flow field analysis for fuel assembly spacer grids or spacer grids with fuel rods were carried out using hydromechanics software.For the spacer grids before and after modification,the calculated hydraulic properties and changes in flow field near the guide vanes were compared.The results show that the rationality of primary modification method for 300 MW fuel assemblies can be validated.  
        关键词：3-D flow field analysis;Fuel assembly;Spacer grid;Spacer grid with fuel rods;Hydraulic property   
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        发布时间：2021-03-05
      • ZHOU Xin ZHU Libing
        Vol. 33, Issue 2, (2010)
        摘要：The boron dilution transient of reactor is simulated using CFX10.0 in this paper.The boron concentration distributions and temperature distributions are obtained for the reactor.The results show that,as temperature of the reactor increases,the resistances fall down and clear water can reach the reactor core quickly,the mixing time between the clear water and borated water reduces,and the mixing effect weakens,with a lower boron concentration at the centre than other parts of the reactor core.  
        关键词：Boron dilution;Transient;Concentration;Temperature   
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        发布时间：2021-03-05
      • LIU Shenghua
        Vol. 33, Issue 2, (2010)
        摘要：In this paper,we compare composite beam design under China’s Code for Design of Steel Structures (GB50017-2003) and the US Specification for the Design,Fabrication,and Erection of Steel Safety-related Structures for Nuclear Facilities (ANSI/AISC N690-1994).Differences and similarities of the two codes are pointed out.This would be useful for engineers and researchers to design or study.  
        关键词：Composite beam;Stability;Deflection;Shear resistant capability   
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        发布时间：2021-03-05
      • REN Yongzhong CHAO Ping XU Dongling
        Vol. 33, Issue 2, (2010)
        摘要：The analog reactor protection system of Qinshan Nuclear Power Plant is to be replaced with a digital system.In this paper,the necessity and scope of the system modernization are addressed.The design philosophy,methodology,design process,system structure design,features of the design and improvements in the system design,are discussed.  
        关键词：QNPP;Digitalized modernization;Reactor protection system;Design   
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        发布时间：2021-03-05
      • LING Yun WANG Xiaowen YUAN Fang
        Vol. 33, Issue 2, (2010)
        摘要：Containment is the enclosure structure of reactor building for a nuclear power plant.It prevents the leakage of radioactive materials out of the NPP in an accident,and is the key component for safety of the NPP.It must be designed to resist the load under severe accident.Earthquake is one of potential natural disaster during the plant service life.And earthquake may result in severe accident.Seismic analysis should be performed for the containment.Prestressed concrete containment should be designed to remain functional under SSE (Safe Shutdown Earthquake).In this work,finite element analysis was use to study the containment earthquake-resistance capacity,the displacement,stress and inner force of the structure under SSE.The results show that the containment structure is adequately safe,and the design can meet the category I requirement of nuclear power plant.  
        关键词：Containment;Prestress;Finite element analysis;SSE behaviour   
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        发布时间：2021-03-05
      • QIAN Hao ZHANG Ming HE Yinbiao JING Yi
        Vol. 33, Issue 2, (2010)
        摘要：The thermocouple column assembly and support structure designed by AREVA is a new structure that has not been used in other nuclear power plants in the world.Structural integrity of the assembly and support is an important factor to the long-term safe operation of the plant.In this work,static analysis under dead weight,FIV influence analysis,modal analysis,seismic analysis,and LOCA analysis were performed.The results indicate that the bolts of initial design cannot bear the load of Service Level D with LOCA.Reasonable improvement measures and its reasons were proposed and assessed.The improved structure was installed in the reactor vessel closure head in the period of NPP shut-down and refueling.  
        关键词：Thermocouple column and support structure;ASME III NG;Structural integrity analysis;Structure improvement and optimize   
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        发布时间：2021-03-05
      • SHEN Qiuping CHEN Zhiqing XU Daoping HUANG Guojun HU Shiguang
        Vol. 33, Issue 2, (2010)
        摘要：The design including fuel bundle-replacing device,fuel bundle dolly and overturn device.The overturn device can overturn fuel bundle.The fuel bundle-replacing device can repair single fuel bundle after aiming at the correct position by the fuel bundle dolly that moves along three dimensions.  
        关键词：Fuel subassembly;Repair;Fuel bundle-replacing device;Fuel bundle dolly;Overturn device   
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        发布时间：2021-03-05
      • XI Meiying LIU Jianwen ZHU Xuefeng GAO Lei ZHENG Chongyu
        Vol. 33, Issue 2, (2010)
        摘要：The guiding device,which performs open and close action reliably,safely and accurately in association with the up and down movement of BPA (Burnable Poison Assembly),is a key point for BPA handling tool design.In a conventional design,four-linkage mechanism is used.However,the pull-link is fairly long and the structure is complicated.In this paper,we propose a new design of the guiding device,where linear cam and roller are used instead.A 3-D simulation study on kinematic and kinetic performance of the new guiding device shows that the design improvement is reasonable and achievable.  
        关键词：BPA handling tool;Guiding device;ADAMS;Simulation   
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        发布时间：2021-03-05
      • WENG Zhimin CHEN Zhiqing
        Vol. 33, Issue 2, (2010)
        摘要：The upending device is used in maintenance of the ANDRITZ RCP internals.This kind of work was done without upending device all over the world,and such a device improves efficiency and safety of the RCP maintenance,and provides convenience for the engineers.It was developed by 3-D modeling in each stage of the design,considering all factors in using,manufacturing and transporting the device,so as to meet practical needs of the device,with video monitoring in assembling and using the device.  
        关键词：ANDRITZ RCP;Maintenance;Upending;Three-dimensional design   
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        发布时间：2021-03-05
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