蒸汽发生器地震反应分析及参数敏感性研究
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摘要
蒸汽发生器是排出反应堆堆芯产生热量的主要设备,是反应堆冷却剂系统压力边界的一部分。其为抗震I类设备,须对其进行地震反应分析。本文建立了蒸汽发生器地震反应分析模型,地震反应分析模型包含汽水分离器组件和管束组件等内件。两个蒸汽发生器模型与一回路管道和压力容器串联,进行地震反应分析,获得地震载荷下的应力结果。同时,本文还就地震反应分析结果对各参数的敏感性做了研究,其中包括另一台蒸汽发生器、支撑、抗振条设置等的影响。研究结果表明,地震反应结果对设备支撑和抗振条设置特别敏感。本文总结了这些参数对分析和设计的指导性意见,供后续核电站蒸汽发生器设计和研发时参考和关注。
Background: The steam generator(SG) serves as the primary means for removing the heat generated within the reactor core and is part of the reactor coolant system(RCS) pressure boundary.Purpose: Seismic analysis is required for SG,whose seismic category is Cat.I.Methods: The analysis model of SG is created with moisture separator assembly and tube bundle assembly herein.The seismic analysis is performed with RCS pipe and Reactor Pressure Vessel(RPV).Results: The seismic stress results of SG are obtained.In addition,parameter sensitivities of seismic analysis results are studied,such as the effect of another SG,support,anti-vibration bars(AVBs),and so on.Our results show that seismic results are sensitive to support and AVBs setting.Conclusions: The guidance and comments on these parameters are summarized for equipment design and analysis,which should be focused on in future new type NPP SG's research and design.
Background: The steam generator(SG) serves as the primary means for removing the heat generated within the reactor core and is part of the reactor coolant system(RCS) pressure boundary.Purpose: Seismic analysis is required for SG,whose seismic category is Cat.I.Methods: The analysis model of SG is created with moisture separator assembly and tube bundle assembly herein.The seismic analysis is performed with RCS pipe and Reactor Pressure Vessel(RPV).Results: The seismic stress results of SG are obtained.In addition,parameter sensitivities of seismic analysis results are studied,such as the effect of another SG,support,anti-vibration bars(AVBs),and so on.Our results show that seismic results are sensitive to support and AVBs setting.Conclusions: The guidance and comments on these parameters are summarized for equipment design and analysis,which should be focused on in future new type NPP SG's research and design.
引文
1孙汉虹,程平东,缪鸿兴,等.第三代核电技术AP1000[M].北京:中国电力出版社,2010 SUN Hanhong,CHENG Pingdong,MIAO Hongxing,et al.Gen III nuclear power technology AP1000[M].Beijing:Chinese Electric Power Press,2010
2 ASME Boiler and Pressure Vessel Code[S],Section III,Rules for Construction of Nuclear Facility Components.New York,1998
3 Fritz R J.The effect of liquids on the dynamic motions of immersed solids,transactions of the ASME[J].Journal of Engineering for Industry,1972,2:167-173
4 Moretti P M,Lowery R L.Hydrodynamic inertia coefficients for a tube surrounded by rigid tubes,transactions of the ASME[J].Journal of Pressure Technology,1976,8:190-193
5汪胜国.国外压水堆核电站蒸汽发生器更换现状及技术开发[J].国外核动力,1996,(3):23-31 WANG Shengguo.Replacement status and technology development of steam generator of foreign pressurized water reactor[J].Foreign Nuclear Power,1996,(3):23-31
2 ASME Boiler and Pressure Vessel Code[S],Section III,Rules for Construction of Nuclear Facility Components.New York,1998
3 Fritz R J.The effect of liquids on the dynamic motions of immersed solids,transactions of the ASME[J].Journal of Engineering for Industry,1972,2:167-173
4 Moretti P M,Lowery R L.Hydrodynamic inertia coefficients for a tube surrounded by rigid tubes,transactions of the ASME[J].Journal of Pressure Technology,1976,8:190-193
5汪胜国.国外压水堆核电站蒸汽发生器更换现状及技术开发[J].国外核动力,1996,(3):23-31 WANG Shengguo.Replacement status and technology development of steam generator of foreign pressurized water reactor[J].Foreign Nuclear Power,1996,(3):23-31
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