Thermal-stress modeling of AP1000 reactor pressure vessel due to transient pressurized thermal shock

被引:0
|
作者
Ma Z. [1 ]
Zhang H. [2 ]
He P. [2 ]
Xu B. [2 ]
Luo Y. [2 ]
Zhou J. [1 ]
机构
[1] Shaanxi Engineering Laboratory for Vibration Control of Aerospace Structures, School of Aerospace, Xi'an Jiaotong University, Xi'an
[2] Key Laboratory of Nuclear Reactor System Design Technology, Nuclear Power Institute of China, Chengdu
关键词
AP1000; Elastic-plastic; Pressurized thermal shock; Reactor pressure vessel; Thermal stress;
D O I
10.1360/N092016-00391
中图分类号
学科分类号
摘要
Reactor pressure vessel is one of the most important components in the reactor system. In case of a loss of coolant accident, low temperature cooling water is injected into the pressurized reactor through the injection nozzle, resulting in severe pressurized thermal shock phenomenon. We performed computational fluid dynamics and thermal-stress analysis of pressurized thermal shock phenomenon of AP1000 reactor. The internal flow field as well as the wall temperature distribution of the pressure vessel was calculated during the transient injection process of cooling water. A bilinear elastic-plastic model was then adopted to analyze the thermal-stress coupling of the pressure vessel due to transient non-uniform temperature distribution. The results indicate that pressurized thermal shock may induce local high stress state and even yielding of material through the injection nozzle, while away from the nozzle the whole structure is fairly safe and retains a low stress state. The methodology and the results presented in the paper provide useful reference for the reliability and safety assessment of nuclear reactors. © 2017, Science Press. All right reserved.
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页码:685 / 691
页数:6
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