论文部分内容阅读
用稳压器液位测量结果表征压水反应堆内冷却剂装量,已不能满足核安全要求;一体化、双壳式的NHR-200(200MW核供热堆)中,传统的差压式核级液位计难以实现其液位测量。为此,基于发热体在气体和液体中放热系数的显著差异,提出了变液位测量为温差测量的加热式铠装热电偶方案,试制了铠装液位传感器,并在模拟实验装置中进行了试验。理论计算和试验结果表明,该传感器原理正确,性能可靠,结构可行,可作为NHR-200堆内水位测量的液位传感器。
With the regulator level measurement results characterize the pressurized water reactor coolant loading, can no longer meet the nuclear safety requirements; integrated, double-hull NHR-200 (200MW nuclear heating reactor), the traditional differential pressure nuclear Level gauge difficult to achieve its level measurement. Therefore, based on the significant difference of exothermic coefficient between gas and liquid in heating element, a scheme of heating type sheathed thermocouple with variable temperature measurement is put forward. The armored liquid level sensor was fabricated and tested in a simulated experiment device Conducted a test. The theoretical calculation and experimental results show that the sensor has the advantages of correct principle, reliable performance and feasible structure, and can be used as a level sensor for water level measurement in the NHR-200 reactor.