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

被引:0
|
作者
Zhao Q. [1 ]
Chen J. [2 ]
Wang G. [3 ]
Zeng W. [1 ]
Zhang D. [1 ]
Yang J. [1 ]
Peng W. [1 ]
机构
[1] Suzhou Nuclear Power Research Institute Co., Ltd., Jiangsu Province, Suzhou
[2] China Nuclear Power Operation Co., Ltd., Guangdong Province, Shenzhen
[3] School of Mechanical and Power Engineering, Shanghai Jiao Tong University, Minhang District, Shanghai
关键词
amplitude; condenser; cooling pipe; flow induced vibration; half side operation; nuclear power plant;
D O I
10.13334/j.0258-8013.pcsee.220994
中图分类号
学科分类号
摘要
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. ©2023 Chin.Soc.for Elec.Eng.
引用
收藏
页码:6332 / 6339
页数:7
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