崔超,黄晨,苏喜平,宿彦京

• 1:中国原子能科学研究院
• 2:北京科技大学

摘要(Abstract)：

快堆先进包壳材料ODS合金(Oxide Dispersion Strengthened Steel)具有优异的抗辐照肿胀性能和高温力学性能,是高性能快堆燃料元件包壳管的主要候选材料。本文概括介绍了ODS合金的研究进展,包括ODS合金的制备方法、力学性能、与钠相容性以及辐照性能等。

关键词(KeyWords)： 快堆;ODS合金;制备工艺;辐照性能;钠相容性

Abstract:

Keywords:

基金项目(Foundation): 国家高技术研究发展计划(863计划)(2011AA050300)

作者(Author): 崔超,黄晨,苏喜平,宿彦京

参考文献(References)：

• [1]A Alamo,V Lambard,M H Mathon,et al.Effects ofthe fabrication route on the microstructure andmechanical behaviourof ODS-14%Cr ferritic alloyincluding neutron irradiation performances[C].International Symposium on,6-7Dec.2003,Kyoto,Japan.
• [2]T Kaito,T Narita,S Ukai,et al.High temperatureoxidation behavior of ODS steels[J].Journal of NuclearMaterials,2004,329-333:1388-1392.
• [3]郭丽娜.化学法制备氧化物弥散强化(ODS)铁素体钢研究[D].北京:北京科技大学,2011.
• [4]彭顺米.化学浸润法ODS铁素体合金的研究[D].北京:北京科技大学,1998.
• [5]郭丽娜,贾成厂,胡本芙,等.制备Y2O3弥散铁素体合金粉末方法的研究[J].粉末冶金技术,2009(27)5.
• [6]Z Oksiuta,N Baluc.Effect of mechanical alloyingatmosphere on the microstructure and charpy impactproperties of an ODS ferritic steel[J].Journal ofNuclear Materials,2009,386-388:426-429.
• [7]Noriyuki Y Iwata,Tong Liu,Peng Dou.Et al.Effect ofMA environment on the mechanical and microstructuralproperties of ODS ferritic steels[J].Journal of NuclearMaterials,2011.
• [8]S Yamashita,Seiichi Watanabe,Somei Ohnuki,et al.Effect of mechanical alloying parameters on irradiationdamage in oxide dispersion strengthened ferritic steels[J].Journal of Nuclear Materials,2000,283-287:647-651.
• [9]刘祖铭,张刘杰,刘咏,等.氧化物弥散强化铁基高温合金研究现状[C].2009全国粉末冶金学术会议论文集,45-51.
• [10]De Castro V,Leguey T,Muoz A,et al.Mechanical andmicrostructural behaviour of Y2O3ODS EUROFER 97[J].Journal of Nuclear Materials,2007,367-370(Part 1):196-201.
• [11]Ukai S,Nishida T,Okada H,et al.Development of OxideDispersion Strengthened Ferrite Steels for FBR CoreApplication,(Ⅰ)Improvement of Mechanical Properties byRecrystallization Processing[J].Journal of NuclearScience and Technology,1997,34(3):256-263.
• [12]P Olier,A Bougault,A Alamo,et al.Effects of theforming processes and Y2O3content on ODS-Eurofermechanical properties[J].Journal of NuclearMaterials,2009,386-388:561-563.
• [13]S Ohtsuka,S Ukai,M Fujiwara.Nano-mesoscopicstructural control in 9Cr-ODS ferritic/martensitic steels.Journal of Nuclear Materials,2006,351:241-246.
• [14]Takeshi Narita,Shigeharu Ukai,Takeji Kaito,et al.Development of two-step softening heat treatment formanufacturing 12Cr-ODS ferritic steel tubes[J].Journal of nuclear science and technology,2004,41(10):1008-1012.
• [15]章林,曲选辉,何新波,等.ODS铁素体钢的研究进展[J].材料科学与工程学报,2009,27(4):639-643.
• [16]Takeji Kaito,Shigeharu Ukai,Satoshi Ohtsuka,et al.Development of ODS Ferritic Steel Cladding for theAdvanced Fast Reactor Fuels[C].Proceeding of Global2005,Tsukuba,Japan,Oct9-13,2005:196.
• [17]T Yoshitake,Y Abe,N Akasaka,et al.Ring-tensileproperties of irradiated oxide dispersion strengthenedferritic/martensitic steel claddings[J].Journal ofnuclear materials,2004,329-333:342-346.
• [18]S Yamashita,N Akasaka,S Ukai,et al.Microstructuraldevelop of a heavily neutron-irradiated ODS ferritic steel(MA957)at elevated temperature[J].Journal of NuclearMaterials,2007,367-370:202-207.
• [19]Toloczko M B,Gelles D S,Garner F A,et al.IrradiationCreep and Swelling from 400 to 600℃of the OxideDispersion Strengthened Ferritic Alloy MA957[J].Journalof Nuclear Materials,2004,329-333(Part 1):352.
• [20]Shigeharu Ukai,Takeji Kaito,Masayuki Seki,et al.Oxide dispersion strengthened(ODS)fuel pinsfabrication for BOR-60irradiation test[J].Journal ofnuclear science and technology,2005,42(1):109-122.
• [21]Takeji Kaito,Shigeharu Ukai,Alexander V.Fuel PinIrradiation Test at up to 5at%Burnup in BOR-60forOxide Dispersion Strengthened Ferritic Steel Claddings[J].Journal of nuclear science and technology,2009,46(6):529-533.