核反应堆液位事故后监测系统  

The Level Monitor System for Nuclear Reactor Vessel During and After Accident

作　　者：王文然[1] 蒋跃元[1] 段泉圣[1] 

机构地区：[1]清华大学核能技术设计研究院

出　　处：《核电子学与探测技术》1997年第3期168-171,共4页Nuclear Electronics & Detection Technology

基　　金：国家"八五"科技攻关课题

摘　　要：本文基于发热体在气体和液体中放热系数的显著差异，开发了一种加热式铠装热偶液位探测器，并在模拟装置中进行了实验。结果表明该探测器原理正确，性能可靠，结构可行。多个探测器构成探测器组件，配以ＳＰＥＣ－２００核级仪表，可实现供热堆压力壳内水位事故后监测。It can not meet the demand of nuclear safety to use the level measured in the pressurizer to show the level in the vessel. It is difficult to monitor the level in the vessel of NHR 200 nuclear heating reactor with present differential pressure liquidometers. A new level detector 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 experiment on the detector is described in this paper. The theoretical calculations and the experimental results show that the detector is correct in principle, reliable in working properties and feasible in structure. The detector assembly consisting of some detectors and the SPEC 200 instruments (E1) are suitable for monitoring the level in the NHR 200 reactor. (

关 键 词：供热堆 液位监视 探测器 核事故 

分 类 号：TL363[核科学技术—核技术及应用]