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作 者:黄茜[1] 余晓菲[1] 齐欢欢[1] 冯志鹏[1] 姜乃斌[1] 宋海洋[1] Huang Qian;Yu Xiaofei;Qi Huanhuan;Feng Zhipeng;Jiang Naibin;Song Haiyang(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)
机构地区:[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610213
出 处:《核动力工程》2019年第1期82-86,共5页Nuclear Power Engineering
基 金:国家自然科学基金(51606180)
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.
关 键 词:蒸汽发生器(SG) 失水事故(LOCA) 摇晃 动力响应 非线性
分 类 号:O327[理学—一般力学与力学基础] TL21[理学—力学]
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