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CNP650型压水堆主管道手工焊接工艺评定 被引量:3

Procedure qualification of CNP650 PWR primary coolant pipeline by manual welding
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摘要 CNP650型压水堆的主管道作为反应堆压力容器堆芯冷却剂的通道,是连接反应堆压力容器、主泵和蒸汽发生器的大型厚壁承压管道。主管道焊接施工是核岛主设备安装的关键路径,是核电建设的重点与难点。焊接工艺评定所提供的数据与焊接经验,对确保主管道焊接施工一次成功,起着非常重要的作用。秦山核电二期扩建工程CNP650型核电站主管道手工焊接工艺评定从模拟现场焊接施工的条件、焊接过程管理、理化试验、焊接变形等方面进行控制,以获得符合技术规范对熔敷金属无损检测、理化性能的要求。焊接工艺评定过程控制为主管道焊接施工提供先决条件。 The primary coolant pipe of CNP650 pressurized water reactor is the enterclose of coolant of reactor core,which is the pressure pipe of large diameter and thickness connected with RPV(reactor pressure vessel) and SG(steam generator) and RCP(reactor coolant pump).The welding construction of primary coolant pipe is the pivotal path of the installation of main equipment of nuclear island and the key and difficult point of the construction of nuclear power plant.The data sheet and welding experience of the WPQ is very important for ensuring the success of the first welding construction.The process control of the manual WPQ of CNP650 nuclear power plant of QinShan Nuclear Power Phase 11 Expansion Project included the simulation condition of the site and the management of welding process and physical and chemical testing and welding deformation,in order to get the deposited metal fitting for the requirements of the NDE and physical and chemical properties of the technical specification.The process control is the prerequisite of the welding construction of primary coolant pipe.
作者 刘先文
出处 《电焊机》 北大核心 2012年第8期72-74,共3页 Electric Welding Machine
关键词 压水堆 主管道 不锈钢 焊接工艺评定 过程控制 pressurized water reactor primary coolant pipe stainless steel welding process qualification process control
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参考文献3

  • 1RCC-M(2000年版+2002年补遗),压水堆核岛机械设备设计制造规则[S].
  • 2HAF602,民用核安全设备无损检验人员资格管理规定[S].国家环境保护总局/国防科学技术工业委员会令第44号.
  • 3HAF603,民用核安全设备焊工焊接操作工资格管理规定[S].国家环境保护总局令第45号.

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