压力容器2017，Vol.34Issue(12)：15-20,6.DOI:10.3969/j.issn.1001-4837.2017.12.003
三代核电厂C型管束热交换器模拟体的动态特性分析和试验研究
Dynamic Analysis and Experiment Study of C-Tubes Heat Exchanger in the Third Generation Nuclear Power Plants
黄庆 1朱甚 1卢文胜 2张振华1
作者信息
- 1. 上海核工程研究设计院有限公司,上海200233
- 2. 同济大学,上海200092
- 折叠
摘要
Abstract
Passive residual heat removal heat exchanger(PRHR HX) is one of the new safety designs in the third generation nuclear power plants.Unlike conventional heat exchangers,the PRHR HX uses supporting rods to keep the tube bundles,shaped like the letter "C",from excessive motion during operation and during seismic events.Since gaps exist between the rods and the tubes,the dynamic characteristics of the rods-tubes assembly is a very complex non-linear problem.To investigate the dynamic characteristics and the seismic capabilities of the PRHR HX,a simplified structure simulating the PRHR HX was manufactured and tested.By comparing with the modal results from the tests,we were able to determine how to model the rod-tube contact conditions and how to simplify the huge number of tubes and rods in the finite element modeling.关键词
非能动余热排出热交换器/C型管束热交换器/模态分析/动态特性Key words
passive residual heat removal heat exchanger/C-tubes heat exchanger/mode analysis/dynamic characteristics分类
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黄庆,朱甚,卢文胜,张振华..三代核电厂C型管束热交换器模拟体的动态特性分析和试验研究[J].压力容器,2017,34(12):15-20,6.
