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作 者:关矞心[1,2] 詹英杰 韩姚磊 李寅 遆文新 孙云雪[3] 张青雨 叶弘熙 Guan Yu-xin;Zhan Ying-jie;Han Yao-lei;Li Yin;Ti Wen-xin;Sun Yun-xue;Zhang Qing-yu;Ye Hong-xi(Suzhou Nuclear Power Research Institute Co.,Ltd.,Jiangsu Suzhou 215004,China;National Engineering Research Center for Nuclear Power Plant Safety&Reliability,Jiangsu Suzhou 215004,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215004 [2]国家核电厂安全及可靠性工程技术研究中心,江苏苏州215004 [3]华能山东石岛湾核电有限公司,山东荣成264312
出 处:《炭素技术》2024年第5期21-27,共7页Carbon Techniques
基 金:国家重大科技专项(2018ZX06906013)。
摘 要:石墨材料在高温气冷堆堆内构件中有重要应用,因此选择适当的机械性能试验标准对于确保核电厂安全运行至关重要。本文针对陶瓷堆内构件材料的机械性能,选取了常用性能指标,如抗拉强度、抗折强度、抗压强度和断裂韧性,并对国内外标准进行了对比分析。通过比较标准之间的技术差异,分析了不同标准对试验结果的影响,为高温气冷堆堆内构件材料机械性能测试和评估提供参考和指导。Graphite materials have important applications in the internal components of high temperature gas-cooled reactors,so selecting appropriate mechanical performance testing standards is crucial for ensuring the safe operation of nuclear power plants.This article selects common performance indicators such as tensile strength,flexural strength,compressive strength,and fracture toughness for the mechanical properties of ceramic stack internal component materials,and compares and analyzes domestic and foreign standards.By comparing the technical differences between standards,the impact of different standards on test results was analyzed,which could be helpful for providing reference and guidance for the mechanical performance testing and evaluation of graphite materials used in hightemperature gas-cooled reactor internals.
分 类 号:TL35[核科学技术—核技术及应用]
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