文章编号：0258-0926(2023)02-0122-07;DOI:10.13832/j.jnpe.2023.02.0122Cr涂层锆合金包壳模拟LOCA试验研究王占伟，严俊，彭振驯，任啟森，廖业宏，李思功，赵亚欢中广核研究院有限公司核燃料与材料研究所，广东深圳，518026摘要：2011年日本福岛核事故暴露传统锆合金燃料包壳在失水事故（LOCA）工况下的安全性问题。为了探究新型Cr涂层锆合金包壳在LOCA工况下的性能，本研究针对物理气相沉积（PVD）工艺涂覆的12~15μm厚度Cr涂层Zr-1Nb合金包壳管，开展模拟LOCA工况下的高温蒸汽氧化-淬火试验，氧化温度为1200℃和1300℃，单面氧化时间为10min和20min，淬火温度约800℃，之后对淬火后试样进行环压测试。结果发现，在研究条件下，Cr涂层未出现剥落，涂层完整；Cr涂层锆合金包壳外表面形成较为致密Cr2O3层，抑制O原子扩散至锆合金基体，阻止锆合金基体被氧化为ZrO2层和α-Zr(O)层，环压测试发现淬火后包壳保持良好塑性。研究表明，在本测试工况下Cr涂层锆合金包壳相比传统锆合金包壳具有更强的抗LOCA事故能力。关键词：Cr涂层锆合金包壳；失水事故（LOCA）；高温蒸汽氧化；淬火；塑-脆性转变中图分类号：TL334文献标志码：AExperimentalStudyofCr-coatedZirconiumAlloyCladdingunderSimulatedLOCAConditionsWangZhanwei,YanJun,PengZhenxun,RenQisen,LiaoYehong,LiSigong,ZhaoYahuanDepartmentofNuclearFuel&Material,ChinaNuclearPowerTechnologyResearchInstituteCo.,Ltd.,Shenzhen,Guangdong,518026,ChinaAbstract:TheFukushimanuclearaccidentinJapanin2011exposedtheinherentsafetyproblemsoftraditionalzirconiumalloyfuelcladdingunderLOCAconditions.ToinvestigatetheperformanceofanewCr-coatedzirconiumalloycladdingunderLOCAconditions,hightemperaturesteamoxidationandquenchingexperimentsundersimulatedLOCAconditionsarecarriedoutfor12~15μmthickCr-coatedZr-1Nballoycladdingtubecoatedbyphysicalvapordeposition(PVD)process,theoxidationtemperatureandoxidationtimewere1200℃,1300℃and10min,20min,respectively,thequenchingwasperformedaround800℃,thenringcompressiontestwasperformedforthequenchedtube.TheresultsindicatedthatnospallingwasfoundforCrcoatingsunderexperimentconditions,intenseCr2O3layerwhichformedontheoutersurfaceofCr-coatedtuberetardedthediffusionofOintozirconiumsubstrate,protectingthe...
