Response of 9Cr-ODS steel to proton irradiation at 400 °C

被引：29
作者：
He, Jianchao [1 ,2 ]
Wan, Farong [1 ]
Sridharan, Kumar [2 ]
Allen, Todd R. [2 ,3 ]
Certain, A. [4 ]
Wu, Y. Q. [5 ,6 ]
机构：
[1] Univ Sci & Technol Beijing, Sch Mat Sci & Engn, Beijing 100083, Peoples R China
[2] Univ Wisconsin, Dept Engn Phys, Madison, WI 53706 USA
[3] EG&G Idaho Inc, Idaho Natl Engn Lab, Idaho Falls, ID 83401 USA
[4] Pacific NW Natl Lab, Richland, WA 99354 USA
[5] Boise State Univ, Dept Mat Sci & Engn, Boise, ID 83725 USA
[6] Ctr Adv Energy Studies, Idaho Falls, ID 83401 USA
来源：
JOURNAL OF NUCLEAR MATERIALS | 2014年 / 452卷 / 1-3期
基金：
中国国家自然科学基金;
关键词：
OXIDE PARTICLES; ATOM-PROBE; DISPERSION; STABILITY; NANOCLUSTERS; SEGREGATION; EVOLUTION; BEHAVIOR;
D O I：
10.1016/j.jnucmat.2014.05.004
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The stability of Y-Ti-O nanoclusters, dislocation structure, and grain boundary segregation in 9Cr-ODS steels has been investigated following proton irradiation at 400 degrees C with damage levels up to 3.7 dpa. A slight coarsening and a decrease in number density of nanoclusters were observed as a result of irradiation. The composition of nanoclusters was also observed to change with a slight increase of Y and Cr concentration in the nanoclusters following irradiation. Size, density, and composition of the nanoclusters were investigated as a function of nanocluster size, specifically classified to three groups. In addition to the changes in nanoclusters, dislocation loops were observed after irradiation. Finally, radiation-induced enrichment of Cr and depletion of W were observed at grain boundaries after irradiation. (C) 2014 Elsevier B. V. All rights reserved.
引用
收藏
页码：87 / 94
页数：8
相关论文
共 35 条
  • [1] On the role of alloy composition and processing parameters in nanocluster formation and dispersion strengthening in nanostuctured ferritic alloys
    Alinger, M. J.
    Odette, G. R.
    Hoelzer, D. T.
    [J]. ACTA MATERIALIA, 2009, 57 (02) : 392 - 406
  • [2] Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation
    Allen, T. R.
    Gan, J.
    Cole, J. I.
    Miller, M. K.
    Busby, J. T.
    Shutthanandan, S.
    Thevuthasan, S.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2008, 375 (01) : 26 - 37
  • [3] Radiation-induced solute segregation in alloys
    Ardell, A. J.
    [J]. MATERIALS ISSUES FOR GENERATION IV SYSTEMS: STATUS, OPEN QUESTIONS AND CHALLENGES, 2008, : 285 - +
  • [4] Asano K., 1988, J NUCL MATER, V928, P155
  • [5] Preparation and structural investigation of nanostructured oxide dispersed strengthened steels
    Balazsi, Cs.
    Gillemot, F.
    Horvath, M.
    Weber, F.
    Balazsi, K.
    Sahin, F. Cinar
    Onuralp, Y.
    Horvath, A.
    [J]. JOURNAL OF MATERIALS SCIENCE, 2011, 46 (13) : 4598 - 4605
  • [6] Radiation stability of nanoclusters in nano-structured oxide dispersion strengthened (ODS) steels
    Certain, A.
    Kuchibhatla, S.
    Shutthanandan, V.
    Hoelzer, D. T.
    Allen, T. R.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2013, 434 (1-3) : 311 - 321
  • [7] Dependence on grain boundary structure of radiation induced segregation in a 9 wt.% Cr model ferritic/martensitic steel
    Field, Kevin G.
    Barnard, Leland M.
    Parish, Chad M.
    Busby, Jeremy T.
    Morgan, Dane
    Allen, Todd R.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2013, 435 (1-3) : 172 - 180
  • [8] Microstructural evolution of proton irradiated T91
    Gupta, G.
    Jiao, Z.
    Ham, A. N.
    Busby, J. T.
    Was, G. S.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2006, 351 (1-3) : 162 - 173
  • [9] Hirata A, 2011, NAT MATER, V10, P922, DOI [10.1038/NMAT3150, 10.1038/nmat3150]
  • [10] Formation mechanism and the role of nanoparticles in Fe-Cr ODS steels developed for radiation tolerance
    Hsiung, Luke L.
    Fluss, Michael J.
    Tumey, Scott J.
    Choi, B. William
    Serruys, Yves
    Willaime, Francois
    Kimura, Akihiko
    [J]. PHYSICAL REVIEW B, 2010, 82 (18):
1234