轻水反应堆-LWR-用包壳材料研究进展-周军

339－10201410MATEＲIALSCHINAVol.33No.9－10Oc[e-mail]10.7502/j.issn.1674－3962.2014.09.03LWＲ710016LWＲ。、。SiC。SiC、4。SiCTG146.4+14A1674－3962201409－0554－06ＲesearchProgressonCladdingMaterialsUsedforLightWaterＲeactorZHOUJunLIZhongkuiWesternEnergyMaterialTechnologiesCo.Ltd.Xi'an710016ChinaAbstractLightwaterreactorLWＲisamajortypeofnuclearpowerreactorintheworld．Becauseoflowneutronab-sorptiongoodcorrosionresistanceandgoodmechanicalpropertieszirconiumalloysarethekeystructuralmaterialsandfunctionalmaterialsforLWＲpowerusedasthecladdingmaterialsoffuelelementsandotherstructuralmaterials．WiththedevelopmentofnuclearpowertechnologythehigherperformancesofthecladdingmaterialareneededthispaperreviewstheresearchandapplicationprogressofnuclearzirconiumalloycladdingandtheresearchanddevelopmentofnewSiCcladdingmaterials．IngeneralzirconiumalloysarestillthemainstructuralmaterialsinnuclearreactorinthecomingdecadescontinuousＲ＆DandimprovedperformanceofnewzirconiumalloysareacommongoalofresearchersaroundtheworlditisnecessarytoincreaseinvestmentsandstrengthenthesupportwithhumanresourcesandfinancialinputinordertoacceleratethepaceofindustrializationofzirconiumalloyswithChineseindependentintellectualpropertyrightswithhighermeltingpointandbettercorrosionresistancerequirementSiCisapotentialmaterialforcladdingoffourthgenera-tionnuclearreactorbutalsoneedstoinvestalotofresearch．KeywordsnuclearreactorzirconiumalloySiCcladding300～400℃、、“1”1。、。、SiC9－10LWＲ、。.。Zr、。、、、、80%。Zr“1”12181/3。、、、、2Zr。Zr－Sn、Zr－NbZr－Sn－Nb3。2050Zr－2Zr－21967。Zr－2“”Zr－2“”“”3。Zr－2NiFeZr－4。360℃Zr－4Zr－21/21/3。Zr－4。Zr－4SnSnZr－4。Zr－4SnZr－4。Zr－1NbZr－Nb。Zr－1NbZr－2Zr－2。Zr－2、Zr－4、Zr－1Nb1SnZr－42。。ph。Zr－4Zr－455GWd/tU4。Zr－SnZr－NbZr－Sn－Nb。2090M5560GWd/tUM5Zr－41/3Zr－41/5Zr－4。M5Zr－4。ZirloBＲ371GWd/tUZr－450%Zr－46。E6357、NDA5、HANA8、PCA。Zr－4Zr－Nb－Sn－Fe－V98GWd/tU。Zirlo、M5、HANAZr－Sn－Nb31、231。10、、。、。2～5。.、、555331w/%Table1Compositionsofthetypicalzirconiumalloysw/%AlloySnNbFeCrNiOCountryZr－21.2～1.7－0.07～0.200.05～0.150.03～0.080.08～0.15/Zr－4con.1.2～1.7－0.18～0.240.07～0.130.0070.08～0.15/Zr－4lowSn1.2～1.5≤50×10－60.18～0.240.07～0.13－0.09～0.16/Zr－2.5Nb－2.5±0.20.08～0.150.008～0.02－0.09～0.13/Zr－1Nb－1±0.150.006～0.012－－0.05～0.07/E6351.2～1.300.95～1.050.34～0.40－－0.05～0.07ＲussiaZIＲLO0.8～1.20.8～1.20.09～0.13－－0.09～0.12USAM5－0.8～1.2－－－0.09～0.15FranceNDA1.00.100.280.160.01－JapanHANA6－1.10.05Cu－－－KoreaN181.00.30.30.1－0.08～0.14ChinaN361.01.00.3－－0.08～0.14China2w/%Table2ＲecentlydevelopednewzirconiumalloysbyUSAw/%AlloySnNbFeCrOpti.ZIＲLOLowSn0.6～0.790.8～1.20.09～0.13－X5A0.50.30.350.25Valloy－－0.11.2V－B1.0－0.513w/%Table3ＲecentlydevelopednewzirconiumalloysbyFrancew/%AlloySnNbFeCrOthersM5－1.0－－S0.10～0.35×10－2O0.13～0.17Opti.M50.1～0.3－0.1～0.3－－J1－1.8－－－J2－1.6－0.1－J3－2.5－－－4w/%Table4ＲecentlydevelopednewzirconiumalloysbyKoreaw/%AlloySnNbFeCrOthersHana－40.41.50.20.1－Hana－50.80.40.350.15Cu0.15w/%Table5ＲecentlydevelopednewzirconiumalloysbyChinaw/%AlloySnNbFeCrOthersC7－1.0－－Cu0.01S0.025SZA－40.80.250.350.10Ge0.05SZA－50.71.00.2－Cu0.05SZA－60.50.50.3－Si0.015、。2060、Zr－2、Zr－4HfZr－2、Hf1Zr－4、。Zr－2Hf。“”SnZr－4Zr－42090Zr－4。Zr－4。。———N36NZ8、N18NZ2。“”N18。N186559－10LWＲ。N18、、、N18。Zr－4N18、、、、Zr－4。N18。“”N18、、。2009～2011863Zr－Nb———C7Zr-1Nb-0.01Cu-0.0025SZL200810232541.1。280mm/500kg9.5mm×0.57mm、10mm、δ0.8mmδ0.3mm。2010～2013N36、。N36t、、KPW259.5mm×0.57mm、、、2012～2013N36。19985。CAST50%M5。、、。200712ZIＲLOAP1000。20134、、“”、。201392.3。、。.、100t。。。、。M5、ZirloN18、N36、C7。Zr－41991Zr－4。M5、ZirloE110。。M5、。Zirlo。75533。。。。。4020113———。SiC49。SiC/SiC①SiC2730℃Zr1852℃2000℃LO-CA。②SiC10。③SiC11。④SiC25%12。⑤。⑥SiCLOCA30%13。⑦。SiC14①。②。③。④。⑤SiCUO2、。SiC.SiC、1。SiC1a1a。SiC/SiC+SiC。SiC。SiC。1SiCabFig.1WestinghouseDuplexSiCcladdingtubeaGraphicrepresentationofstructureandbphotoofmaterialobject.SiC+SiC+23。3、3。SiCSiCSiC。SiC、8559－10LWＲ。。2SiCFig.2PhotoofprototypeSiCceramicmatrixcompositetestingrods3Fig.3Schematicdiagramofthethree－layercladdingtubeunderconsideration。1。2。。3SiC、4。1ZhaoWenjinZhouBangxinMiaoZhi．J．AtomicEnergyScienceandTechnology200539suppl.2－9．2WeiXiaoweiShenBaoluo．J．ChineseJournalofＲareMetals2002267304－306．3YangWendou．ＲeactorMaterialsScienceM．BeijingAtomicEnergyPress2006259－289．4ZhouBangxin．J．TransactionofMaterialsandHeatTreatment19971838－15．5LiPeizhi．J．ＲareMetalMaterialsandEngineering19992903185－186．6MarolonJPGarnerGBesluPetal．UpdateontheDevelop-mentofAdvancedZirconiumAlloysforＲWＲFuelＲodCladdingsC//ProceedingsofANSFuelPerformanceConferenceinPort-landUSA．USAANS1997331－336．7NikulinaAVMarkelovVAPeregudMMetal．ZirconiumAlloyE635asaMaterialforFuelFodCladdingandOtherCom-ponentsofVVEＲandＲBMKCoresC//BradleyEＲSabolGP．ZirconiumintheNuclearIndustry．PhiladelphiaAmericaSo-cietyforTestingandMaterials1996785－804．8JeongYHParkSYLeeMHetal．Out-of-PileandIn-PilePerformanceofAdvancedZirconiumAlloysHANAforHighBurn-UpFuelJ．JournalofNuclearScienceandTechnology2006439977－983．9HaynerGOShaberELMiziaＲE．IdahoNationalEngineer-ingandEnvironmentalLaboratoryJ．IdahoIdahoFalls2004．10KatohYSneadLLNozawaTetal．ThermophysicalandMe-chanicalPropertiesofNear-StoichiometricFibe