Effects of Fe self-ion irradiation on a low carbon MX-ODS steel at 550°C

被引:2
作者
Xu, Yuwen [1 ]
Yun, Di [1 ,2 ]
Yan, Xu [1 ]
Zhang, Ping [1 ]
Yan, Wei [3 ,4 ]
Li, Yanfen [3 ,4 ]
Li, Chao [5 ]
Li, Jiao [5 ]
Zhang, Tongmin [6 ]
Li, Jun [6 ]
Zhou, Junjun [6 ]
Kang, Long [6 ]
Lu, Chenyang [1 ]
机构
[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian, Peoples R China
[2] Xi An Jiao Tong Univ, State Key Lab Multiphase Flow, Xian, Peoples R China
[3] Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Shenyang, Peoples R China
[4] Chinese Acad Sci, Inst Met Res, Shi Changxu Innovat Ctr Adv Mat, Shenyang, Peoples R China
[5] Xi An Jiao Tong Univ, Instrumental Anal Ctr, Xian, Peoples R China
[6] Chinese Acad Sci, Inst Modern Phys IMP, Lanzhou, Peoples R China
关键词
ODS steel; ion irradiation; void swelling; oxide nano-precipitate; MX phase; RADIATION RESPONSE; PHASE INSTABILITY; SECONDARY PHASES; FERRITIC STEELS; ALLOY; STABILITY; ELECTRON; PARTICLES; EVOLUTION; DIFFUSION;
D O I
10.3389/fenrg.2022.988745
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
Oxide Dispersion Strengthened (ODS) steels with nano-scale oxides have become one of the candidate materials used in advanced nuclear reactor systems. A novel MX-ODS steel with extremely low carbon content was irradiated with 3 MeV Fe ions at 550 & DEG;C up to peak damage of 70 dpa. The steel contains uniformly distributed Y2O3 nano-precipitates with an average size of 3.5 nm and a number density of 5 x 10(22)/m(3). A V-rich shell was found surrounding the core of Y, O, and Si at some particles. Two types of large precipitates, Y-Ta-Si oxides, and VN, were observed in the steel instead of carbides. Voids of very small size are present due to irradiation and the calculated void swelling was only 0.004%, suggesting good irradiation tolerance of the MX-ODS steel in this study. Fine and dense oxide nano-precipitates and their shell-core structure remained stable while the shape of large precipitates changed after irradiation.
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页数:12
相关论文
共 52 条
[1]   Mechanism of instability of carbides in Fe-TaC alloy under high energy electron irradiation at 673 K [J].
Abe, Hiroaki ;
Ishizaki, Takahiro ;
Kano, Sho ;
Li, Feng ;
Satoh, Yuhki ;
Tanigawa, Hiroyasu ;
Hamaguchi, Dai ;
Nagase, Takeshi ;
Yasuda, Hidehiro .
JOURNAL OF NUCLEAR MATERIALS, 2014, 455 (1-3) :695-699
[2]   Investigation of oxide particles in unirradiated ODS Eurofer by tomographic atom probe [J].
Aleev, A. A. ;
Iskandarov, N. A. ;
Klimenkov, M. ;
Lindau, R. ;
Moeslang, A. ;
Nikitin, A. A. ;
Rogozhkin, S. V. ;
Vladimirov, P. ;
Zaluzhnyi, A. G. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 409 (02) :65-71
[3]  
Biersack J. F. Z. J. P., 2013, SRIM PROGRAM
[4]   Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation [J].
Chen, Tianyi ;
Aydogan, Eda ;
Gigax, Jonathan G. ;
Chen, Di ;
Wang, Jing ;
Wang, Xuemei ;
Ukai, S. ;
Garner, F. A. ;
Shao, Lin .
JOURNAL OF NUCLEAR MATERIALS, 2015, 467 :42-49
[5]   Ab-initio based modeling of diffusion in dilute bcc Fe-Ni and Fe-Cr alloys and implications for radiation induced segregation [J].
Choudhury, S. ;
Barnard, L. ;
Tucker, J. D. ;
Allen, T. R. ;
Wirth, B. D. ;
Asta, M. ;
Morgan, D. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 411 (1-3) :1-14
[6]   Analytical characterization of secondary phases and void distributions in an ultrafine-grained ODS Fe-14Cr model alloy [J].
de Castro, V. ;
Leguey, T. ;
Auger, M. A. ;
Lozano-Perez, S. ;
Jenkins, M. L. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) :217-220
[7]   Stability of nanoscale secondary phases in an oxide dispersion strengthened Fe-12Cr alloy [J].
de Castro, V. ;
Marquis, E. A. ;
Lozano-Perez, S. ;
Pareja, R. ;
Jenkins, M. L. .
ACTA MATERIALIA, 2011, 59 (10) :3927-3936
[8]   Microstructural characterization of Y2O3 ODS-Fe-Cr model alloys [J].
de Castro, V. ;
Leguey, T. ;
Munoz, A. ;
Monge, M. A. ;
Pareja, R. ;
Marquis, E. A. ;
Lozano-Perez, S. ;
Jenkins, M. L. .
JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 :449-452
[9]   Modeling the impact of radiation-enhanced diffusion on implanted ion profiles [J].
Doyle, Peter J. ;
Benensky, Kelsa M. ;
Zinkle, Steven J. .
JOURNAL OF NUCLEAR MATERIALS, 2018, 509 :168-180
[10]   Characterisation of the influence of vanadium and tantalum on yttrium-based nano-oxides in ODS Eurofer steel [J].
Fu, J. ;
Davis, T. P. ;
Kumar, A. ;
Richardson, I. M. ;
Hermans, M. J. M. .
MATERIALS CHARACTERIZATION, 2021, 175