摘要
CAP1400是我国具有自主知识产权的三代核电技术,代表着我国核电技术的高起点发展,其稳压器的重型支撑结构与AP1000技术相比有一定的差异,具有结构复杂、焊接难度大、尺寸控制要求高等特点。本文以国核压水堆示范工程的稳压器重型支撑的制造为例,详细描述了其上部支撑(环形梁)的焊接及变形控制技术。通过实施验证,焊缝质量和组件变形情况均满足上游文件要求,标志着解决了这一核电核心结构件的制造难题。
CAP1400 is the third generation of nuclear power technology with independent intellectual property rights in China,which represents the high starting point of the development of nuclear power technology in China.The heavy support structure of its pressurizer is different from that of AP1000 technology.It has the characteristics of complex structure,difficult welding and high size control requirements.In this paper,the welding and deformation control technology of the upper support(annular beam) is described in detail by taking the manufacture of the heavy support of the pressurizer of the nuclear pressurized water reactor demonstration project as an example.Through implementation verification,the weld quality and component deformation meet the requirements of upstream documents,which indicates that the manufacturing problem of this nuclear power core structural component has been solved.
作者
邢昊
刘玉平
李鹏飞
王黎
XING Hao;LIU Yuping;LI Pengfei;WANG Li
出处
《大型铸锻件》
2024年第3期15-19,共5页
Heavy Casting and Forging