核电厂稳压器波动管热震荡应力评估研究

发布时间：2018-02-25 23:34

本文关键词： 波动管热震荡疲劳分析　出处：《应用数学和力学》2014年S1期 　论文类型：期刊论文

【摘要】：典型的管道分析会对所有预期的热载荷进行评估,研究表明核电厂稳压器波动管会经受非预期的并伴随热分层现象产生的热震荡载荷。利用理论分析方法推导出便于求解的半解析公式,并对其进行了工程实例验证,从而验证推导的半解析公式的正确性。同时采用半解析公式评估了核电厂典型的稳压器波动管在热分层温差不同时热震荡载荷导致管道内壁产生的局部峰值应力,并根据ASME规范评估了稳压器波动管热震荡应力对管道疲劳的影响。研究结果表明,核电厂在升温或停堆期间热震荡载荷对波动管的疲劳使用系数影响较小;在核电厂长时间的正常运行期间,当稳压器波动管横截面垂直方向的温差达到临界值时,热震荡载荷对波动管的疲劳使用系数影响非常显著。
[Abstract]:A typical pipeline analysis evaluates all expected thermal loads, The study shows that the fluctuating tube of the voltage regulator of nuclear power plant will undergo unexpected thermal shock load caused by thermal stratification. The semi-analytical formula is derived by using the theoretical analysis method and verified by an engineering example. At the same time, the semi-analytical formula is used to evaluate the local peak stress on the inner wall of the pipe caused by the thermal stratification temperature difference at the same time, and the semi-analytical formula is used to evaluate the local peak stress of the typical pressurizer fluctuating tube of the nuclear power plant at the same time of the thermal stratification temperature difference. According to the ASME code, the influence of thermal oscillation stress on pipe fatigue is evaluated. The results show that the thermal oscillation load has little effect on the fatigue coefficient of the fluctuating tube during the heating or shutdown period of the nuclear power plant. During a long period of normal operation of the nuclear power plant, when the temperature difference in the vertical direction of the fluctuating tube reaches the critical value, the thermal oscillation load has a very significant effect on the fatigue coefficient of the fluctuating tube.
【作者单位】：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;
【分类号】：TM623

【相似文献】