秦山核电二期工程稳压器的自主设计与国产化  

Indigenous Design and Local Manufacture of Pressurizer for Qinshan Phase II NPP Project

作　　者：郑剑[1] 詹可纯 王振全 

机构地区：[1]中国核动力研究设计院,成都610041

出　　处：《核动力工程》2003年第z1期168-172,共5页Nuclear Power Engineering

摘　　要：采用分析法进行稳压器的设计。为了减小热应力的危害,改善接头的受力状态,采取了降低热疲劳的措施。在RCC-M 1级锻件的基础上,又增加了砷、锡、锑、硼等有害元素的考核指标以及金相检验的要求。稳压器的支承设计采用下封头整体锻出的凸台与裙座支承筒对接焊连接。对波动接管及其热屏蔽套管的瞬态温度场分布、喷雾接管材料的疲劳性能和塑性累积变形,以及反应堆冷却剂系统特殊构件(包括波动接管)的瞬态传热特性进行了试验和分析研究,用流体力学软件FLUENT对构件的传热性能进行了数值计算,得到了良好的试验和计算结果。The pressurizer is designed based on the analytical method. In order to mitigate the thermal stress and improve the status of the stress applied on the joint, measures to reduce the thermal fatigue have been adopted. As for the forged piece, besides the previous requirement of RCCM-1, it also defined the acceptance specifications on the dangerous elements, such as arsenic, tin, antimony and boron, and requirements of metallographic examination. The pressurizer is supported by the butt-welded connection between the integrated forged boss on the lower endplate and supporting cylinder on the skirt support. The transient temperature distribution of the surge connector and its thermal shielding sleeve, the fatigue performance and the accumulated plastic deformation of the material of the spray connector, and the transient heat transfer of the special components in the reactor coolant system (including surge connector) have been tested and analyzed. The heat transfer performance of the components is calculated by hydrodynamics software FLUENT, and good results have been obtained.

关 键 词：核电站 稳压器 自主设计 国产化 

分 类 号：TL353+.14[核科学技术—核技术及应用]