【作者】 任成； 孙艳飞； 杨星团；

【Author】 REN Cheng;SUN Yan-fei;YANG Xing-tuan;Institute of Nuclear and New Energy Technology,Tsinghua University;

【机构】 清华大学核能与新能源技术研究院；

【摘要】 高温气冷堆是一种在我国取得迅速发展的先进核能系统。反应堆堆芯内温度在正常运行条件下限值为1200℃,在事故工况下应被限制在1600℃以下。有别于其他堆型,高温堆堆芯中形成了一种由碳砖和石墨基燃料元件构成的石墨环境。这种特殊高温石墨环境给接触式直接温度测量带来很大困难。常见的热电偶保护套管材料在极端高温石墨环境下极易被腐蚀或炭化,造成脆断和失效。清华大学核能与新能源技术研究院建立了一个材料性能测试装置,模拟了高温堆内的高温石墨环境,实验温度可达1600℃,覆盖了高温气冷堆正常运行和事故工况下的整个温度范围。在实验装置中采用多支特制热电偶进行了测试实验,设计出适用于高温气冷堆极端高温石墨环境下的热电偶材料和结构形式。更多还原

【Abstract】 The high temperature gas-cooled reactor(HTGR) is an advanced nuclear power system that has being developed rapidly in China.The temperature in the reactor can reach 1200℃ under normal operation condition and should be limited under 1600, under accident condition.Unlike other types of reactors,the high-temperature reactor core is a graphite environment composed of carbon bricks and graphite based fuel elements.This special high-temperature graphite environment poses great difficulties for direct contact temperature measurement.Common thermocouple protective sleeve materials,which are commonly used in high-temperature conditions,can be easily corroded or carbonized in this graphite extreme environment at high temperatures.A material performance test apparatus was built in Institute of Nuclear and New Energy Technology of Tsinghua University to simulate a testing environment with high temperature and graphite environment similar as that confronted in the real reactor core of HTGR.Test temperature in the apparatus can be elevated up to 1600℃,which covers the whole temperature range of the normal operation and accident condition of HTGR.Temperature measurements using specially-made thermocouples were implemented in the test apparatus.Applicable materials and structure of thermocouples were screened out for the extreme environment of high temperature gas-cooled reactor.更多还原