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| CORROSION BEHAVIOR OF Zr-Sn-Nb ALLOY |
| Wenjin Zhao;Zhi Miao;Hongman Jiang |
| 中国核动力研究设计院核燃烧及材料国家级重点实验室 |
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Cite this article:
Wenjin Zhao; Zhi Miao; Hongman Jiang. CORROSION BEHAVIOR OF Zr-Sn-Nb ALLOY. J Chin Soc Corr Pro, 2002, 22(2): 124-128 .
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Abstract The corrosion behaviors of Zr-Sn-Nb alloy (N18, N36) developed in China have been studied by out-of-pile autoclave in 360℃ wate r with 70 μg/g Li,in 400℃ and 500℃ high pressure steam.The results show that the nodular corrosion for two kinds of alloys did not occur after 500h,and Zr-4 alloy did after 4h in high-pressure oxygen at 500℃;that the weight gain of N18 samples is lower than Zr-4,and of N36 is higher than Zr-4 after 245 days in 400 ℃ high pressure steam;that the weight gain for two kinds of alloys samples is o nly 16%-25% that of Zr-4 after 300 days in 360℃ water with 70 μg/g Li.N18 allo y possesse s good corrosion resistance in both high temperature water and high pressure ste am.Addition of alloying element Nb in Zr-Sn binary system,on the one hand,solid solution of Nb in α-Zr can resist the detrimental effect of C,N impurities on c orrosion behavior,on the another hand,the formation of α-Nb second phase partic les and their uniform distribution in alloy can reduce greatly the oxidation rat io in high temperature water and high pressure steam.The nonuniform growth of o xide film occurs at the oxide film/metal interface,and that of oxide film become s more distinct after oxidant transition.
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Received: 03 December 2001
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[1]EuckenCM ,FindenPT ,etal.ZirconiumintheNuclearIndustry[A ].8thInternationalSymposium,ASTMSTP 1023[C].VanSwamLFP ,EuckenCM ,Eds.Philadelphia:AmericanSocietyforTestingandMaterials,1989,113
[2]GarzarolliG ,SteinbergE ,WeidingerHC .Microstructureandcorro sionstudiesforoptimizedPWRandBWRzircaloycladding,Zirconi umintheNuclearIndustry[A ].8thInternationalSymposium.ASTMSTP 1023[C].VanSwamLFP ,EuckenCM ,Eds.Philadelphia:AmericanSocietyforTestingandMaterials,1989,202
[3]ZhouBX ,ZhaoWJ ,etal.Aninvestigationonimprovingcorrosionbehaviorofzircaloy-4[J].ChineseJournalofNuclearScienceandEngineering,1995,15(3);242(周邦新,赵文金等.改善Zr-4合金耐腐蚀性能的研究[J].核科学与工程,1995,15(3):242)
[4]RomaryH ,DeydierD .TechnicalCommitteeMeetingonInfluenceofWaterChemistryonFuelCladdingBehavior,Rez(nearPrague)[M ].TheCzechRepublic.1993,10:4-8
[5]SabolGP ,ComstockRJ,WeinerRA ,etal.ZirconiumintheNu clearIndustry[A ].10thInternationalSymposium,ASTMSTP1245[C].GardeAM ,BradleyER ,Eds.Philadelphia:AmericanSo cietyforTestingandMaterials,1994,724.
[6]NikulinaAV ,MarkelovVA ,PeregudMM ,etal.ZirconiumintheNuclearIndustry[A].11thInternationalSymposium,ASTMSTP1295[C],BradleyER ,SabolGP ,Eds.WestConshohocken:Amer icanSocietyforTestingandMaterials,1996,785.
[7]ZhaoWJ.DevelopmentofnewcladdingmaterialsforPWRfuelele mentinFrance[J].NuclearPowerEngineering,2000,21(3):278(赵文金.法国压水堆燃料元件新一代包壳材料的发展[J].核动力工程,2000,21(3):278)
[8]IAEA -TECDOC -996.Watersidecorrosionofzirconiumalloysinnuclearpowerplants[C].IAEA ,Vienna,1998
[9]YamateK ,OeA ,HayashiM ,etal.BurnupExtensionofJapanesePWRFuels[A ].ANSFuelPerformanceConferenceinPortland(USA)[C].March2-6,1997.
[10]ZhouBX ,ZhaoWJ,etal.Astudyofnewzirconiumalloys[A].SymposiaProceedingsofCMRS ,BiomaterialandEconmaterials[C].Beijing:ChemicalIndustryPress,1997,183(周邦新,赵文金等.新锆合金的研究[A].96’中国材料研讨会,生物及环境,Ⅲ-2[C].北京:化学工业出版社,1997,183)
[11]ZhaoWJ,ZhouBX .InvestigationoftheintermetallicprecipitatesinZr-4[J].NuclearPowerEngineering,1991,12(5);67(赵文金,周邦新.Zr-4合金中第二相的研究[J].核动力工程,1991,12:67-72
[12]ComstockRJ,SchoenbergerG ,SabolGP .ZirconiumintheNucle arIndustry[A].11thInternationalSymposium.ASTMSTP 1295[C],BradleyER ,SabolGP ,Eds.WestConshohocken:AmericanSocietyforTestingandMaterials,1996,710
[13]ZhouBX ,etal.Theeffectofwaterchemistryonthecorrosionbe haviorofzirconiumalloys[J].NuclearPowerEngineering,2000,21(5):439(周邦新等.水化学对锆合金耐腐蚀性能影响的研究[J].核动力工程,2000,21(5):439) |
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