学术论文

      巴基斯坦核电机组C3/C4堆芯测温用铠装热电偶的研制

      Thedevelopment of sheathed thermocouple of in-core temperature measurement for Pakistan Nuclear Power Plant C3/C4

      摘要:
      介绍了巴基斯坦核电机组C3/C4堆芯测温铠装热电偶的研制.堆芯测温铠装热电偶用于测量反应堆堆芯冷却剂出口温度,用来计算平均温度、最高温度和区域温度最高差值等信息,并参与堆芯液位密度补偿和堆芯过冷度裕度的计算.堆芯测温铠装热电偶已通过核级性能和环境鉴定试验,证明其满足核安全(1 E)级的要求,并成功地应用于中国援巴核电项目C3/C4核电机组.堆芯测温铠装热电偶的研制成功填补了国内空白.
      Abstract:
      This article introduces the development and qualification test of sheathed thermocouple of in-core temperature measurement for Pakistan Nuclear Power Plant C3/C4 . The in-core sheathed ther-mocouples are used to measure the outlet temperatures of in-core coolant which are used to calculate the average temperature, maximum temperature and the maximum temperature difference value in the reactor core area, and they are also used to calculate the water density of the core level compensation and the core super-cooling degree of margin. The in-core sheathed thermocouples have been completed the nu-clear safety class performance and environmental qualification test and have been proved to meet the re-quirements of the nuclear safety class (1E), and have been used successfully in Pakistan Nuclear Power Plant C3/C4. The successful development of in-core sheathed thermocouple fills the domestic blank.
      作者: 孙智超 [1] 孙炯 [1] 朱陈洛 [1] 查美生 [2]
      Author: SUN Zhichao [1] SUN Jiong [1] ZHU Chenluo [1] ZHA Meisheng [2]
      作者单位: 宁波奥崎自动化仪表设备有限公司,浙江 宁波,315020 清华大学 核能技术设计研究院,北京,102201
      年,卷(期): 2017, (6)
      分类号: TM623
      在线出版日期: 2018年1月4日