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作 者:蔡逢春[1] 黄旋[1] 沈平川[1] 叶献辉[1]
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,四川成都610213
出 处:《原子能科学技术》2018年第2期269-275,共7页Atomic Energy Science and Technology
基 金:国家自然科学基金资助项目(51606180)
摘 要:泵致脉动压力是核电站中引起主设备部件疲劳失效的主要原因之一。本文建立了蒸汽发生器传热管的泵致脉动压力载荷表达式,并建立不同弯曲半径的传热管有限元模型,对蒸汽发生器传热管在泵致脉动压力载荷下的动力学响应进行了研究。结果表明:34、64、94、114、124、144排传热管附近的频率、振型对泵致脉动压力最为敏感;包络泵致脉动压力作用下,最大应力出现在32排传热管上;传热管在泵致脉动压力载荷作用下,泵致脉动压力载荷的轴频频率对结构响应的贡献最大。本文分析结果为蒸汽发生器传热管在泵致脉动压力载荷下的磨损分析提供了参考。Pump-induced pressure pulsation is a main factor that caused the fatigue failure of equipments in the nuclear power plants.In this paper,functions for the pumpinduced pressure pulsation in the heat transfer tubes of the steam generator were derived and the finite element model for all heat transfer tubes with different bending radii was established.Based on these models the dynamic behavior of heat transfer tubes under the pump-induced pressure pulsation was studied.The results show that the frequency and mode of the heat transfer tubes of row 34,64,94,114,124 and 144 are the most sensitive to the pump-induced pressure pulsation.The maximum stress appears on the heat transfer tube of row 32 under the enveloped pump-induced pressure pulsation,and the rotation frequency of the pump-induced pulsating pressure load has the greatest contribution to the structure response under the pump-induced pressure pulsation.This paper offers a reference for wear analysis of heat transfer tubes in steam generator under pump-induced pressure pulsation.
分 类 号:TL364[核科学技术—核技术及应用]
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