Advanced fission and fusion reactors require high-performance alloys with outstanding microstructure and property stability in ultra-severe service environment including high temperature and high pressure, intense neutron irradiation and long service life. Oxide dispersion strengthened (ODS) steels have been considered as the most promising candidate as fuel cladding in Gen. Ⅳ reactor and structural materials in fusion blanket. Based on neutron irradiation damage, this paper reviews the latest research progress of irradiation-resistant ODS steels, focusing on the alloy design and advanced nanoscale second-phase particles characterization techniques.
Lv Z, Chen H, Chen C , et al. Preliminary neutronics design and analysis of helium cooled solid breeder blanket for CFETR[J]. Fusion Engineering and Design, 2015,95:79.
[3]
Peng X, Ye M, Song Y , et al.Engineering conceptual design of CFETR divertor[J].Fusion Engineering and Design, 2015, 98-99:1380.
[4]
Li M . Structural design and thermal-hydraulic analysis research of helium cooled solid blanket for CFETR[D]. Hefei: University of Science and Technology of China, 2015(in Chinese).
Odette G R, Alinger M J, Wirth B D . Recent developments in irradiation-resistant steels[J]. Annual Review of Materials Research, 2008,38:471.
[7]
郁金南 . 材料辐照效应[M]. 北京: 化学工业出版社, 2007.
[8]
Lv Z . Development and prospect of nano-structured ods steels for fusion reactor first wall application[J]. Atomic Energy Science and Technology, 2011,45(9):1105(in Chinese).
Zinkle S J, Snead L L . Designing radiation resistance in materials for fusion energy[J]. Annual Review of Materials Research, 2014,44(1):241.
[11]
McClintock D A, Sokolov M A, Hoelzer D T , et al. Mechanical properties of irradiated ODS-EUROFER and nanocluster strengthened 14YWT[J]. Journal of Nuclear Materials, 2009,392(2):353.
[12]
Henry J, Averty X, Alamo A . Tensile and impact properties of 9Cr tempered martensitic steels and ODS-FeCr alloys irradiated in a fast reactor at 325 degrees C up to 78 dpa[J]. Journal of Nuclear Materials, 2011,417(1-3):99.
[13]
Yamashita S, Akasaka N, Ukai S , et al. Microstructural development of a heavily neutron-irradiated ODS ferritic steel ( MA957) at elevated temperature[J]. Journal of Nuclear Materials, 2007, 367-370(1):202.
[14]
Miao P, Hoelzer D T, Bentley J. , The transport and fate of helium in nanostructured ferritic alloys at fusion relevant He/dpa ratios and dpa rates[J].Journal of Nuclear Materials, 2007, 367-370(10):399.
[15]
Kurtz R J, Odette G R, Yamamoto T , et al.The transport and fate of helium in martensitic steels at fusion relevant He/dpa ratios and dpa rates[J].Journal of Nuclear Materials, 2007, 367- 370(10):417.
[16]
Toloczko M B, Gelles D S, Garner F A , et al.Irradiation creep and swelling from 400 to 600 ℃ of the oxide dispersion strengthened ferritic alloy MA957[J].Journal of Nuclear Materials, 2004, 329- 333(1):352.
[17]
Butterworth G J . Low activation structural materials for fusion[J]. Fusion Engineering and Design, 1989,11(s1-2):231.
[18]
Kohyama A, Hishinuma A, Gelles D S , et al.Low-activation ferritic and martensitic steels for fusion application[J].Journal of Nuclear Materials, 1996, 233- 237(1):138.
[19]
Lindau R, M?slang A, Rieth M , et al.Present development status of EUROFER and ODS-EUROFER for application in blanket concepts[J].Fusion Engineering and Design, 2005, 75- 79:989.
[20]
Zinkle S J . Advanced materials for fusion technology[J]. Fusion Engineering and Design, 2005,74(1-4):31.
[21]
Kimura A, Kasada R, Kohyama A , et al. Recent progress in US-Japan collaborative research on ferritic steels R&D[J]. Journal of Nuclear Materials, 2007, 367- 370(Part 1):60.
[22]
Klueh R L . Reduced-activation bainitic and martensitic steels for nuclear fusion applications[J]. Current Opinion in Solid State and Materials Science, 2004,8(3-4):239.
[23]
van der Schaaf B, Gelles D S, Jitsukawa S , et al.Progress and critical issues of reduced activation ferritic/martensitic steel development[J].Journal of Nuclear Materials, 2000, 283- 287:52.
[24]
Lindau R Schirra M. , First results on the characterisation of the reduced-activation-ferritic-martensitic steel EUROFER[J].Fusion Engineering and Design, 2001, 58- 59:781.
[25]
Huang Q Y, Li C J, Li Y F , et al. R&D status of China low activation martensitic steel[J]. Chinese Journal of Nuclear Science and Engineering, 2007,27(1):41(in Chinese).
Huang Q , Team F D S. Development status of CLAM steel for fusion application[J]. Journal of Nuclear Materials, 2014,455(1-3):649.
[28]
Wang P, Chen J, Fu H , et al. Effect of N on the precipitation behaviours of the reduced activation ferritic/martensitic steel CLF-1 after thermal ageing[J]. Journal of Nuclear Materials, 2013,442(1-3,Supplement 1):S9.
Mansur L K . Theory and experimental background on dimensional changes in irradiated alloys[J]. Journal of Nuclear Materials, 1994,216:97.
[31]
Lindau R, M?slang A, Schirra M , et al. Mechanical and microstructural properties of a hipped RAFM ODS-steel[J].Journal of Nuclear Materials, 2002, 307- 311(Part 1):769.
[32]
Baluc N, Boutard J L, Dudarev S L , et al. Review on the EFDA work programme on nano-structured ODS RAF steels[J]. Journal of Nuclear Materials, 2011,417(1-3):149.
[33]
Klueh R L, Shingledecker J P, Swindeman R W , et al. Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys[J]. Journal of Nuclear Materials, 2005,341(2-3):103.
[34]
He P, Klimenkov M, M?slang A , et al. Correlation of microstructure and low cycle fatigue properties for 13.5Cr1.1W0.3Ti ODS steel[J]. Journal of Nuclear Materials, 2014,455(1-3):167.
[35]
He P, Lindau R, Moeslang A , et al. The influence of thermomechanical processing on the microstructure and mechanical properties of 13.5Cr ODS steels[J]. Fusion Engineering and Design, 2013,88(9-10):2448.
[36]
Zinkle S J, Ice G E, Miller M K , et al. Advances in microstructural characterization[J]. Journal of Nuclear Materials, 2009, 386- 388:8.
[37]
Hsiung L, Fluss M, Tumey S , et al. HRTEM study of oxide nanoparticles in K3-ODS ferritic steel developed for radiation tolerance[J]. Journal of Nuclear Materials, 2011,409(2):72.
[38]
Kishimoto H, Alinger M J, Odette G R , et al. TEM examination of microstructural evolution during processing of 14CrYWTi nanostructured ferritic alloys[J].Journal of Nuclear Materials, 2004, 329- 333(Part 1):369.
[39]
Klimenkov M, Lindau R , M?slang A. TEM study of internal oxidation in an ODS-Eurofer alloy[J]. Journal of Nuclear Materials, 2009, 386- 388:557.
[40]
Klimiankou M, Lindau R, M?slang A . HRTEM Study of yttrium oxide particles in ODS steels for fusion reactor application[J]. Journal of Crystal Growth, 2003,249(1-2):381.
[41]
Klimiankou M, Lindau R ,M?slang A. TEM characterization of structure and composition of nanosized ODS particles in reduced activation ferritic-martensitic steels[J]. Journal of Nuclear Materials, 2004, 329- 333(Part 1):347.
[42]
Klimiankou M, Lindau R, M?slang A , et al. TEM study of PM 2000 steel[J]. Powder Metallurgy, 2005,48(3):277.
[43]
Wu Y, Haney E M, Cunningham N J , et al. Transmission electron microscopy characterization of the nanofeatures in nanostructured ferritic alloy MA957[J]. Acta Materialia, 2012,60(8):3456.
[44]
Williams C A, Unifantowicz P, Baluc N , et al. The formation and evolution of oxide particles in oxide-dispersion-strengthened ferritic steels during processing[J]. Acta Materialia, 2013,61(6):2219.
[45]
Klimenkov M, Lindau R M?slang A . New insights into the structure of ODS particles in the ODS-Eurofer alloy[J].Journal of Nuclear Materials, 2009, 386-388:553.
[46]
Hirata A, Fujita T, Liu C T , et al. Characterization of oxide nanoprecipitates in an oxide dispersion strengthened 14YWT steel using aberration-corrected STEM[J]. Acta Materialia, 2012,60(16):5686.
[47]
Hirata A, Fujita T, Wen Y R , et al. Atomic structure of nanoclusters in oxide-dispersion-strengthened steels[J]. Nature Materials, 2011,10(12):922.
[48]
Zhou B X . Three dimensional atom probe-an instrument for microstructure investigation of materials with analyzing atoms one by one[J]. Chinese Journal of Nature, 2005,27(3):125(in Chinese).
Kelly T F, Miller M K . Invited review article: Atom probe tomography[J]. The Review of Scientific Instruments, 2007,78(3):031101.
[50]
Miller M K, Hoelzer D T, Kenik E A , et al. Nanometer scale precipitation in ferritic MA/ODS alloy MA957[J]. Journal of Nuclear Materials, 2004, 329-333(Part 1):338.
[51]
Miller M K, Hoelzer D T, Kenik E A , et al. Stability of ferritic MA/ODS alloys at high temperatures[J]. Intermetallics, 2005,13(3-4):387.
[52]
Miller M K, Russell K F, Hoelzer D T . Characterization of precipitates in MA/ODS ferritic alloys[J]. Journal of Nuclear Materials, 2006,351(1-3):261.
[53]
Mathon M H, Perrut M, Zhong S Y , et al. Small angle neutron scattering study of martensitic/ferritic ODS alloys[J]. Journal of Nuclear Materials, 2012,428(1-3):147.
[54]
Williams C A, Marquis E A, Cerezo A , et al. Nanoscale characterisation of ODS-Eurofer 97 steel: An atom-probe tomography study[J]. Journal of Nuclear Materials, 2010,400(1):37.
[55]
M?slang A, Adelhelm C, Heidinger R . Innovative materials for energy technology[J]. International Journal of Materials Research, 2008,99(10):1045.
[56]
Ratti M, Leuvrey D, Mathon M H , et al. Influence of titanium on nano-cluster (Y,Ti,O)stability in ODS ferritic materials[J].Journal of Nuclear Materials, 2009, 386- 388:540.
[57]
Alinger M J, Odette G R, Hoelzer D T . On the role of alloy composition and processing parameters in nanocluster formation and dispersion strengthening in nanostuctured ferritic alloys[J]. Acta Materialia, 2009,57(2):392.
[58]
Dumont M, Commin L, Morfin I , et al. Chemical composition of nano-phases studied by anomalous small-angle X-ray scattering: Application to oxide nano-particles in ODS steels[J]. Materials Characterization, 2014,87:138.
[59]
Ohnuma M, Suzuki J, Ohtsuka S , et al. A new method for the quantitative analysis of the scale and composition of nanosized oxide in 9Cr-ODS steel[J]. Acta Materialia, 2009,57(18):5571.