传热管双端断裂事故工况下炭堆内构件材料性能退化行为研究  

Study on the ageing behavior of carbon reactor internal materials under double end fracture accident of a heat transfer tube

作　　者：韩姚磊 詹英杰 关矞心[1,3] 李寅 遆文新 孙云雪[2] 彭群家 Han Yao-lei;Zhan Ying-jie;Guan Yu-xin;Li Yin;Ti Wen-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;National Engineering Research Center for Nuclear Power Plant Safety&Reliability,Jiangsu Suzhou 214005,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 [3]国家核电厂安全及可靠性工程技术研究中心,江苏苏州214005

出　　处：《炭素技术》2024年第5期17-20,共4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：高温气冷堆炭堆内构件由含B4C的石墨材料制备而成。在蒸汽发生器传热管双端发生断裂事故工况时,将约有600 kg水汽泄漏到回路,导致炭堆内构件发生腐蚀,使其性能退化,影响高温气冷堆的长期安全可靠运行。以炭堆内构件材料为研究对象,研究了模拟传热管双端断裂事故工况下炭堆内构件材料的腐蚀行为和力学性能行为变化规律。研究结果发现随时间增加,材料密度下降,腐蚀程度增大;材料抗拉强度、抗弯强度、抗压强度、断裂韧性均随时间增加而下降,分析认为炭堆内构件材料表面孔洞的腐蚀可能促进裂纹萌生,内部孔洞的腐蚀可能促进裂纹扩展。The carbon reactor internals of the high-temperature gas-cooled reactor are made of graphite materials containing B4C.When a double ends fracture accident occurs in the heat transfer tube of a steam generator,vapor of about 600 kg will leak into the primary circuit,causing oxidation of the carbon reactor internals,resulting in performance degradation and affecting the long-term safe and reliable operation of the high temperature gas-cooled reactor.This article takes the carbon reactor internal materials as the research object,and studies the corrosion behavior and mechanical performance behavior under the simulated heat transfer tube double ends fracture ac-cident conditions.It was found that as time increases,the material density decreases and both the roughness and the degree of corrosion increases.The tensile strength,bending strength,compressive strength,and fracture toughness of materials all decrease with time.Analysis suggests that corrosion of surface pores in carbon reactor internal materials may promote crack initiation,while corrosion of internal pores may promote crack propagation.

关 键 词：高温气冷堆 炭堆内构件 腐蚀 力学性能 

分 类 号：TL35[核科学技术—核技术及应用]