Assessment of phase stability of oxide particles in different types of 15Cr-ODS ferritic steels under 6.4 MeV Fe ion irradiation at 200 °C

被引:22
作者
Song, Peng [1 ]
Kimura, Akihiko [1 ]
Yabuuchi, Kiyohiro [1 ]
Dou, Peng [2 ]
Watanabe, Hideo [3 ]
Gao, Jin [1 ]
Huang, Yen-Jui [1 ]
机构
[1] Kyoto Univ, Inst Adv Energy, Kyoto 6110011, Japan
[2] Chongqing Univ, Coll Mat Sci & Engn, Chongqing 400030, Peoples R China
[3] Kyushu Univ, Res Inst Appl Mech, Kasuga, Fukuoka 8168580, Japan
关键词
Ion-irradiation; Ballistic dissolution; Amorphization; Re-precipitation; FeCrAl(Zr)-ODS steel; DISPERSION-STRENGTHENED STEEL; RADIATION TOLERANCE; INDUCED AMORPHIZATION; NEUTRON-IRRADIATION; ODS; EVOLUTION; ALLOYS; NANOCLUSTERS; DISSOLUTION; RESISTANCE;
D O I
10.1016/j.jnucmat.2019.151953
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Three types of 15Cr-ODS ferritic steels were irradiated with 6.4 MeV Fe3+ at 200 degrees C up to a nominal displacement damage of 10 dpa to assess the phase stability of different sorts of oxide particles under ion-irradiation. Before the irradiation, dominant oxide particles in (Y, Ti) ODS, (Y, Al) ODS and (Y, Zr) ODS steels were identified as Y-Ti-O, Y-Al-O, and Y-Zr-O types, respectively, and the difference in the average diameters and number densities of oxide particles among the three ODS ferritic steels was as small as within the factor of two. After the irradiation, the number densities and volume fractions of oxide particles in all the three ODS steels decreased with increasing dpa regardless of the different dispersion morphologies, chemical compositions and crystal structures of the particles, which was interpreted in terms of the dominant mechanism of ballistic dissolution with a moderate occurrence of radiation-enhanced diffusion (RED) and re-precipitation of the nano-clusters. Almost no significant difference in the phase stability of oxide particles was recognized among the three types of ODS ferritic steels. However, normalized volume fractions of Y-Zr-O particles were slightly bigger than those of Y-Ti-O and Y-Al-O at high damage levels. Moreover, Y-Al-O particles underwent the loss of moire fringe because of the amorphization of oxide particles, while the delta-phase Y4Zr3O12 in (Y, Zr) ODS still maintained crystalline structure even at similar to 20 dpa/local. It is concluded that Y-Zr-O particles are more stable than Y-Al-O and possibly Y-Ti-O particles. (C) 2019 Elsevier B.V. All rights reserved.
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页数:17
相关论文
共 65 条
[1]  
Adylov T., 1988, J INORG CHEM, V33, P1062
[2]   DIFFRACTION CONTRAST FROM SPHERICALLY SYMMETRICAL COHERENCY STRAINS [J].
ASHBY, MF ;
BROWN, LM .
PHILOSOPHICAL MAGAZINE, 1963, 8 (91) :1083-&
[3]   Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties [J].
Aydogan, E. ;
Weaver, J. S. ;
Carvajal-Nunez, U. ;
Schneider, M. M. ;
Gigax, J. G. ;
Krumwiede, D. L. ;
Hosemann, P. ;
Saleh, T. A. ;
Mara, N. A. ;
Hoelzer, D. T. ;
Hilton, B. ;
Maloy, S. A. .
ACTA MATERIALIA, 2019, 167 :181-196
[4]   Selection of fuel cladding material for nuclear fission reactors [J].
Azevedo, C. R. F. .
ENGINEERING FAILURE ANALYSIS, 2011, 18 (08) :1943-1962
[5]   Heavy-ion irradiation effects on structures and acid dissolution of pyrochlores [J].
Begg, BD ;
Hess, NJ ;
Weber, WJ ;
Devanathan, R ;
Icenhower, JP ;
Thevuthasan, S ;
McGrail, BP .
JOURNAL OF NUCLEAR MATERIALS, 2001, 288 (2-3) :208-216
[6]   Chromium enrichment on the habit plane of dislocation loops in ion-irradiated high-purity Fe-Cr alloys [J].
Bhattacharya, A. ;
Meslin, E. ;
Henry, J. ;
Pareige, C. ;
Decamps, B. ;
Genevois, C. ;
Brimbal, D. ;
Barbu, A. .
ACTA MATERIALIA, 2014, 78 :394-403
[7]   Quasi in-situ energy dispersive X-ray spectroscopy observation of matrix and solute interactions on Y-Ti-O oxide particles in an austenitic stainless steel under 1 MeV Kr2+ high temperature irradiation [J].
Brooks, Adam J. ;
Yao, Zhongwen ;
Daymond, Mark R. ;
Yu, Hongbing ;
Kirk, Mark A. ;
Zhou, Zhangjian ;
Zhang, Guangming .
ACTA MATERIALIA, 2017, 141 :241-250
[8]  
Buntushkin V., 1971, INORG MATER+, V7, P1456
[9]   Radiation stability of nanoclusters in nano-structured oxide dispersion strengthened (ODS) steels [J].
Certain, A. ;
Kuchibhatla, S. ;
Shutthanandan, V. ;
Hoelzer, D. T. ;
Allen, T. R. .
JOURNAL OF NUCLEAR MATERIALS, 2013, 434 (1-3) :311-321
[10]   Temperature dependent dispersoid stability in ion-irradiated ferritic-martensitic dual-phase oxide-dispersion-strengthened alloy: Coherent interfaces vs. incoherent interfaces [J].
Chen, Tianyi ;
Gigax, Jonathan G. ;
Price, Lloyd ;
Chen, Di ;
Ukai, S. ;
Aydogan, Eda ;
Maloy, S. A. ;
Garner, F. A. ;
Shao, Lin .
ACTA MATERIALIA, 2016, 116 :29-42