SG LOCA摇晃动力响应数值分析
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摘要
经过合理的简化与等效处理,建立了国内某3代核电站的蒸汽发生器(SG)非线性有限元模型,将其与反应堆冷却剂环路(RCL)串联,开展了SG失水事故(LOCA)摇晃动力响应数值分析,得到了作用在SG传热管上的应力极值及其随管径的变化规律,并获得了作用在上部支承上的载荷。将本文方法与传统解耦法进行对比,结果表明:SG的解耦对摇晃动力响应有较大影响,应采用与RCL耦联的计算方式。
Through reasonable simplification and equivalence finish, a detailed nonlinear finite element model of steam generator(SG) of a domestic 3 rd generation nuclear power plant(NPP) is established. This model is then connected with the reactor coolant loop(RCL) to carry out the analysis of dynamic response for SG LOCA shaking. By calculation, the maximum absolute stresses of SG heat transfer tube bundles and its variation with tube diameter and reacting forces of upper supports are obtained. In order to study the effect of SG decoupling from the RCL on the shaking dynamic response, a comparative study of decoupling/coupling methods is developed. Results show that SG decoupling has a significant impact on the calculation result, and the calculation method of coupling is more closer to the real situation and should be recommended.
Through reasonable simplification and equivalence finish, a detailed nonlinear finite element model of steam generator(SG) of a domestic 3 rd generation nuclear power plant(NPP) is established. This model is then connected with the reactor coolant loop(RCL) to carry out the analysis of dynamic response for SG LOCA shaking. By calculation, the maximum absolute stresses of SG heat transfer tube bundles and its variation with tube diameter and reacting forces of upper supports are obtained. In order to study the effect of SG decoupling from the RCL on the shaking dynamic response, a comparative study of decoupling/coupling methods is developed. Results show that SG decoupling has a significant impact on the calculation result, and the calculation method of coupling is more closer to the real situation and should be recommended.
引文
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[2]毛庆,曾忠秀,张毅雄,等.反应堆冷却剂系统LOCA非线性动力分析初步研究[C].第十一届全国反应堆结构力学会议,2000.
[3]齐欢欢,曾忠秀,张毅雄,等.基于ANSYS二次开发的反应堆冷却剂系统LOCA非线性动力分析[J].核动力工程,2011,32(S1):31-37.
[4]毛庆,余红星,肖忠,等.核反应堆地震和失水事故下结构动力分析研究[J].核动力工程,2002,23(1):35-39.
[5]Peter Hermansky,Marian Krajcovic.The numerical simulation of the WWER440/V213 reactor pressure vessel internals response to maximum hypothetical Large-break loss of coolant accident[J].Nuclear Engineering and Design,2011,241(4):131-137.
[6]齐欢欢,沈平川,吴万军,等,燃料组件导向管事故工况应力计算方法研究[J].应用数学和力学,2016,37(5):67-72.
[7]周云清,刘家正,朱丽兵.地震加LOCA下的燃料组件安全分析研究[J].核动力工程,2011,32(S1):43-49.
[8]Fritz R J.The effect of liquids on the dynamic motions of immersed solids,transactions of the ASME[J].Journal of Engineering for Industry,1972,87(2):167-173.
[9]Moretti P M,Lowery R L.Hydrodynamic inertia coefficients for a tube surrounded by rigid tubes[J].Jounal of Pressure Vessel Technology,1976,98(3):188-190
[10]王勖成.有限单元法[M].北京:清华大学出版社,2003.
[2]毛庆,曾忠秀,张毅雄,等.反应堆冷却剂系统LOCA非线性动力分析初步研究[C].第十一届全国反应堆结构力学会议,2000.
[3]齐欢欢,曾忠秀,张毅雄,等.基于ANSYS二次开发的反应堆冷却剂系统LOCA非线性动力分析[J].核动力工程,2011,32(S1):31-37.
[4]毛庆,余红星,肖忠,等.核反应堆地震和失水事故下结构动力分析研究[J].核动力工程,2002,23(1):35-39.
[5]Peter Hermansky,Marian Krajcovic.The numerical simulation of the WWER440/V213 reactor pressure vessel internals response to maximum hypothetical Large-break loss of coolant accident[J].Nuclear Engineering and Design,2011,241(4):131-137.
[6]齐欢欢,沈平川,吴万军,等,燃料组件导向管事故工况应力计算方法研究[J].应用数学和力学,2016,37(5):67-72.
[7]周云清,刘家正,朱丽兵.地震加LOCA下的燃料组件安全分析研究[J].核动力工程,2011,32(S1):43-49.
[8]Fritz R J.The effect of liquids on the dynamic motions of immersed solids,transactions of the ASME[J].Journal of Engineering for Industry,1972,87(2):167-173.
[9]Moretti P M,Lowery R L.Hydrodynamic inertia coefficients for a tube surrounded by rigid tubes[J].Jounal of Pressure Vessel Technology,1976,98(3):188-190
[10]王勖成.有限单元法[M].北京:清华大学出版社,2003.