CPR1000机组凝汽器半侧安全运行评价方法研究  

Study on Safety Evaluation Method of Condenser Half Side Operation for CPR1000 Units

作　　者：赵清森[1] 陈杰 汪国山[3] 曾维鹏 张鼎[1] 杨杰[1] 彭伟頔 ZHAO Qingsen;CHEN Jie;WANG Guoshan;ZENG Weipeng;ZHANG Ding;YANG Jie;PENG Weidi(Suzhou Nuclear Power Research Institute Co.,Ltd.,Suzhou 215004,Jiangsu Province,China;China Nuclear Power Operation Co.,Ltd.,Shenzhen 518000,Guangdong Province,China;School of Mechanical and Power Engineering,Shanghai Jiao Tong University,Minhang District,Shanghai 200240,China)

机构地区：[1]苏州热工研究院有限公司,江苏省苏州市215004 [2]中广核核电运营有限责任公司,广东省深圳市518000 [3]上海交通大学机械与动力工程学院,上海市闵行区200240

出　　处：《中国电机工程学报》2023年第16期6332-6339,共8页Proceedings of the CSEE

基　　金：中广核集团尖峰计划项目(R-2019SZPT11TM)。

摘　　要：我国CPR1000压水堆核电机组半侧运行期间凝汽器多次发生冷却管断裂事件,造成严重的安全影响和经济损失,半侧运行时支撑板跨距偏大引起的弹性汽流激振是主要可能原因之一。美国热交换协会等相关设计规范中并没有给出半侧运行时的计算方法。结合冷却管振动基本理论,推导出凝汽器支撑板跨距计算的数学模型,可以适用于压水堆核电机组凝汽器半侧运行的跨距计算。该文以某压水堆核电项目为例,对比不同凝汽器的冷却管评价模型,利用某核电站半侧运行的实际工况数据对评价方法进行验证,提出Connors系数(Kc)值2.3及风险因子0.8可以适用于压水堆核电站凝汽器钛管安全运行的评价准则。基于振动碰磨理论计算出的凝汽器安全跨距最小为556mm,现场应变初步测量结果也证实该方法是足够保守的,可利用该方法进行支撑板跨距的设计校核。During the half side operation of PWR CPR1000 units,the condenser cooling pipes have broken for many times,resulting in serious safety impact and economic loss.Elastic steam flow induced vibration caused by large spacing during half side operation is one of the main possible reasons.The corresponding calculation method is not given in relevant design specifications such as Heat Exchange Institute(HEI).Combined with the basic theory of cooling pipe vibration,the mathematical model used in condenser support plate spacing calculation is deduced,which can be applied to the spacing calculation of condenser half side operation at nuclear power units.Taking a PWR nuclear power project as an example the different condensers cooling pipe evaluation models is verified by using actual working condition data of half side operation in the nuclear power plant.It is proposed that Connors coefficient KC value is 2.3 and the risk factor is 0.8,which can be applied to the evaluation criteria for condenser safe operation in the nuclear power plant.The minimum condenser spacing is 556mm based on the vibration impact wear theory.The actual amplitude measurement results also confirm that this model is conservative enough,which can be used for design reference verification in condenser spacing design.

关 键 词：核电厂 凝汽器 半侧运行 冷却管 流致振动 振幅 

分 类 号：TK264[动力工程及工程热物理—动力机械及工程]