摘要
传统的二代压水反应堆主要是采取鼓风机鼓风的方式对控制棒驱动机构(Control Rod Drive Mechanism,CRDM)进行强制通风冷却,该冷却方式耗能较大且无法保证绝对安全可靠。本文针对于大亚湾核电站中CRDM群的布置方式,采用中广核新型的EMC-B型控制棒驱动机构的结构及材料物性参数,运用了计算流体力学(Computational Fluid Dynamics,CFD)分析方法,研究了当采用空气自然循环冷却方式时,CRDM群及各线圈的温度分布,探索对CRDM群采用空气自然循环冷却方式的可行性。模拟分析结果表明:总体来看,处于外围和中心位置处的CRDM的线圈温度,要比中间区域的CRDM线圈温度高;对于给定计算工况,各线圈的最高温度为198°C,低于限制温度(200°C),表明对于所研究的CRDM群,依靠空气的自然对流,可以对CRDM进行有效冷却。计算结果可为新型CRDM群分布设计提供参考。
Background： In the second generation pressurized water reactor, the Control Rod Drive Mechanism （CRDM） is mainly cooled by the blast blower, which consumes more energy and is of lower security. Based on the layout of the CRDM group in the Daya Bay nuclear power plant, the EMC-B type of CRDM is taken as research object. Purpose： The temperature distribution of the CRDM group was simulated to verify the feasiblity of natural circluation cooling of air. Methods： Several Computational Fluid Dynamics （CFD） based programs were employed for this research. Firstly, Pro/ENGINEER was applied to establish the 3D model of the CRDM group; then the geometrical model was meshed with ICEM; finally, the flow field and temperature distribution were solved by using FLUENT. Results： The temperature field of the CRDM can be divided into three regions, and the temperature of the middle CRDM was highest, while the temperature of the region between the middle and outside regions was lowest due to the relative weak convection. The highest coil temperature is 198 ℃, below the limit value of 200℃. Conclusion： The CRDM and the coils may be cooled effectively by natural convection of air under given conditions.
出处
《核技术》
CAS
CSCD
北大核心
2014年第3期71-75,共5页
Nuclear Techniques
