陶瓷堆内构件热老化行为研究现状  

Research status on the thermal ageing behaviour of ceramic internals

作　　者：韩姚磊 詹英杰 遆文新[1] 李寅 关矞心[1] 孙云雪 彭群家 Han Yao-lei;Zhan Ying-jie;Ti Wen-xin;Li Yin;Guan Yu-xin;Sun Yun-xue;Peng Qun-jia(Suzhou Nuclear Power Research Institute Co.,Ltd.,Jiangsu Suzhou 214005,China;Huaneng Shandong Shidao Bay Nuclear Power Co.,Ltd.,Shandong Rongcheng 264312,China)

机构地区：[1]苏州热工研究院有限公司,江苏苏州214005 [2]华能山东石岛湾核电有限公司,山东荣成264312

出　　处：《炭素技术》2023年第5期25-29,共5页Carbon Techniques

基　　金：国家科技重大专项“高温堆示范工程关键设备老化防腐技术研究”(2018ZX06906013)。

摘　　要：高温气冷堆陶瓷堆内构件采用石墨材料制备。在长期服役过程中由于氧化性气体杂质及事故工况引入水蒸气等原因,石墨将发生氧化,导致陶瓷堆内构件热老化,影响高温气冷堆的长期安全可靠运行。本文对有关陶瓷堆内构件用石墨材料的氧化行为研究、机械性能和物理化学性能研究等进行了综述,并在此基础上总结了陶瓷堆内构件热老化行为研究现状中存在的问题,为后续相关研究提供参考。The high temperature gas-cooled reactor ceramic internals are manufactured by graphite materials.During the long-term service graphite will be oxidized by oxidizing gas impurities and the introduced water vapor in accident conditions,leading to thermal aging of the ceramic internals and affecting the long-term safety and reliable operation of high temperature gas-cooled reactors.This paper reviews the oxidation behaviors,mechanical performance and physicochemical properties of graphite materials used in ceramic in-ternals,and summarizes the remaining problems in the research of thermal ageing behaviour of ceramic internals.

关 键 词：陶瓷堆内构件 氧化 热老化 高温气冷堆 

分 类 号：TL352.24[核科学技术—核技术及应用]