|本期目录/Table of Contents|

[1]孙智超,孙 炯,朱陈洛,等.巴基斯坦核电机组C3/C4堆芯测温用铠装热电偶的研制[J].工业仪表与自动化装置,2017,(06):29-32.[doi:1000-0682（2017）06-0029-04]
　SUN Zhichao,SUN Jiong,ZHU Chenluo,et al.The development of sheathed thermocouple of in-core temperature measurement for Pakistan Nuclear Power Plant C3/C4[J].Industrial Instrumentation & Automation,2017,(06):29-32.[doi:1000-0682（2017）06-0029-04]
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巴基斯坦核电机组C3/C4堆芯测温用铠装热电偶的研制

《工业仪表与自动化装置》[ISSN:1000-0682/CN:61-1121/TH]

卷:
期数:
2017年06期
页码:
29-32
栏目:
出版日期:
2017-12-15

文章信息/Info

Title:
The development of sheathed thermocouple of in-core temperature measurement for Pakistan Nuclear Power Plant C3/C4
作者:
孙智超1; 孙 炯1; 朱陈洛1; 查美生2
1.宁波奥崎自动化仪表设备有限公司，浙江 宁波315020；2.清华大学 核能技术设计研究院，北京102201
Author(s):
SUN Zhichao1; SUN Jiong1; ZHU Chenluo1; ZHA Meisheng2
1.Ningbo Auqi Auto-instrument Equipment Co.,Ltd, Zhejiang Ningbo 315020,China;2．Institute of Nuclear Energy Technology,Tsinghua University,Beijing 102201,China
关键词:
核电站; 堆芯温度测量; 铠装热电偶; 热电偶接插件
Keywords:
nuclear power plant;  in-core temperature measurement;  sheathed thermocouple;  thermocouple connector
分类号:
TM623
DOI:
1000-0682（2017）06-0029-04
文献标志码:
A
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(1E)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 thermocouples 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 nuclear safety class performance and environmental qualification test and have been proved to meet the requirements 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.

参考文献/References:

[1] EJ 660—92 核级铠装热电偶[S].中国核工业总公司, 1992. [2] 中华人民共和国国家质量监督检验检疫总局.GB/T 12727—2002 核电厂安全级系统电气设备质量鉴定[S]. [3] ASTM E235-03 Standard Specification for Thermocouples, Sheathed,Type K and Type N,for Nuclear or for Other High-Reliability Applications. [4] IEC 60780—1998, Nuclear Power Plants Electrical Equipment of the Safety System Qualification[S]. Geneva, Switzerland, International Electro Technical Commission, 1998. [5] RCCE—2002,Design and Construction Rules for Electrical Components of Nuclear Islands[S]. Paris, France, AFCEN, 2002. [6] IEEE Std.323—2003, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations[S]. Institute of Electrical and Electronics Engineers, Piscataway, NJ, 2003.

相似文献/References:

[1]王延华,王智勇,王国龙.核电站温度仪表应用分析[J].工业仪表与自动化装置,2016,(02):106.
　WANG Yanhua,WANG Zhiyong,WANG Guolong.An application and analysis of temperature instrument in nuclear power plant[J].Industrial Instrumentation & Automation,2016,(06):106.

备注/Memo

备注/Memo:
收稿日期：2017-02-27 作者简介：孙智超(1989)，男，工程师，2015年毕业于英国利兹大学，主要从事热工仪表和传感器的研究和制造工作。 通讯作者：查美生(1945)，男，教授，1970年毕业于清华大学，主要从事核电仪表和传感器的研发工作。zhameisheng@aliyun.com
更新日期/Last Update: 2017-12-01