摘要
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。
It can not meet the demand of nuclear safety to use the level measured in the pressurizer to show the reactor vessel level and it is difficult to monitor the level in the vessel of NHR 200(200MW nuclear heating reactor) with traditional differential pressure liquidometers. So, a new level sensor which is designed according to the heat transfer difference between water (or liquid) and steam (or gas) and the relationship between the level and the differential temperature is developed. The simulating experiments about the sensor is discribed in this paper. The theoretical calculations and the experimental results show that the sensor is correct in principle, reliable in working properties and feasible in structure. The sensor is suitable for monitoring the level in the NHR 200.
出处
《清华大学学报（自然科学版）》
EI
CAS
CSCD
北大核心
1996年第11期105-109,共5页
Journal of Tsinghua University(Science and Technology)
基金
国家"八五"科技攻关项目
关键词
供热堆
液位测量
传感器
水位测量
nuclear heating reactor(NHR)
level monitor
sensor
