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STUDY ON THE SHAKING DYNAMIC RESPONSE OF STEAM GENERATOR LOCA

机译:汽轮机局部振动的动力响应研究

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Dynamic response research of steam generator loss of coolant accident (SG LOCA) is essential for the reliability and safety consideration. According to the differences of LOCA loading phenomena, two types of LOCA loads affect the SG: rarefaction wave travels through the primary fluid in the U-tubes, and the SG shakes due to reactor coolant loop(RCL) motions transmitted by the primary loop piping, former loading phenomena evaluation is called SG rarefaction analysis while latter is called shaking analysis. This paper place particular emphasis on shaking analysis. At present, the published literatures about LOCA mainly focus on RCL LOCA, reactor LOCA and fuel assembly LOCA, few reports concentrate on shaking dynamic response analysis of SG LOCA. Both Westinghouse and AREVA's methods according to their research reports are to decouple the SG from the RCL: This method results in low computational efficiency as RCL LOCA and SG LOCA are evaluated separately and the decoupling error is uncertainty, meanwhile, in the vicinity of the nodes where the displacements are imposed, distorted reaction forces are usually found. Through reasonable simplification and equivalence, a detailed nonlinear FEM model of steam generator (SG) of a China 3rd generation nuclear power plant (NPP) is established, this model is then connected with the reactor coolant loop (RCL) to carry out the SG LOCA shaking dynamic response analysis. By calculation, the maximum absolute stresses of SG heat transfer tube bundle and its variation with tube diameter and upper supports reacting forces are obtained. In order to study the effect of SG decoupling from the RCL on shaking dynamic response, a comparative study of decoupling /coupling methods is conducted. Results shows that SG decoupling has a significant impact on the calculation result, the calculation method of coupling is more closer to the real situation and worthy to recommended. Related analytical procedures and calculation results lay the foundation for future SG shaking dynamic analysis and SG design of subsequent power plants.
机译:蒸汽发生器失水事故的动态响应研究(SG LOCA)对于可靠性和安全性考虑至关重要。根据LOCA载荷现象的差异,两种类型的LOCA载荷会影响SG:稀疏波穿过U型管中的主流体,并且SG由于主回路管道传输的反应堆冷却剂回路(RCL)运动而发生振动,前者的载荷现象评估称为SG稀疏度分析,而后者则称为振动分析。本文特别强调了振动分析。目前,关于LOCA的已发表文献主要集中在RCL LOCA,反应堆LOCA和燃料组件LOCA上,鲜有报道集中于对SG LOCA的动态响应分析。根据研究报告,Westinghouse和AREVA的方法都是将SG与RCL分离:由于分别评估RCL LOCA和SG LOCA,并且去耦误差不确定,因此该方法的计算效率较低。在施加位移的地方,通常会发现扭曲的反作用力。通过合理简化和等效,建立了中国第三代核电厂蒸汽发生器(SG)的详细非线性有限元模型,然后将该模型与反应堆冷却剂回路(RCL)连接以进行SG LOCA颤抖的动态响应分析。通过计算,获得了SG传热管束的最大绝对应力及其随管径和上支座反作用力的变化。为了研究SG从RCL去耦对振动动态响应的影响,进行了去耦/耦合方法的比较研究。结果表明,SG解耦对计算结果有显着影响,耦合的计算方法更接近实际情况,值得推荐。相关的分析程序和计算结果为将来的SG振动分析和后续电厂的SG设计奠定了基础。

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