核供热堆堆芯出口冷却剂温度测量方法和误差估计  

The Measuring Method and Error Estimation of Temperature for Coolant at Outlet of Nuclear Heating Reactor

作　　者：查美生[1] 沈健[1] 马昌文[1] 陈实[1] 

机构地区：[1]清华大学核能技术设计研究院,北京102201

出　　处：《自动化仪表》2002年第7期13-16,共4页Process Automation Instrumentation

摘　　要：提出了 2 0 0MW核供热反应堆堆芯出口冷却温度测量的新方法 ,即将铠装热电偶插入位于燃料元件盒支承格子板上的空间正交沟槽内 ,其测量端与燃料侧的侧平面平齐 ,热电偶测得的温度代表燃料元件盒中心区域冷却剂的温度。根据误差分析 ,在NHR -2 0 0运行工况下堆芯冷却剂出口温度的最大误差是±2 0℃ ,满足工程精度的要求。The new method for measuring the temperature of coolant at outlet of 200MW nuclear heating reactor is stated, i.e. inserting the armored thermocouple into the space of the crossing ditch of the latticed supporting plates of fuel element box, the measuring end is flushed with the side plane of fuel side, Thus the temperature measured reflects the temperature of the coolant in the middle of the fuel element box. According to the error analysis the maximal error of outlet temperature of outlet coolant under operation of NHR-200 is +/-2 0 degree C which is met with the design requirement.

关 键 词：冷却剂 误差估计 铠装热电偶 核供热反应堆 测温 

分 类 号：TL36[核科学技术—核技术及应用]