Microstructural investigation of the stability under irradiation of oxide dispersion strengthened ferritic steels

被引:90
|
作者
Monnet, I
Dubuisson, P
Serruys, Y
Ruault, MO
Kaïtasov, O
Jouffrey, B
机构
[1] CEA Saclay, SRMA, DEN, F-91191 Gif Sur Yvette, France
[2] CEA Saclay, SRMP, DMN, DEN, F-91191 Gif Sur Yvette, France
[3] CNRS, IN2P3, CSNSM, F-91405 Orsay, France
[4] Ecole Cent Paris, LMSS Mat, F-92295 Chatenay Malabry, France
关键词
D O I
10.1016/j.jnucmat.2004.05.018
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Some fuel pin cladding made from a ferritic steel reinforced by titanium and yttrium oxides were irradiated in the French experimental reactor Phenix. Microstructural examination of this alloy indicates that oxides undergo dissolution under irradiation. This irradiation shows the influence of dose and, in a smaller part, of temperature. In order to better understand the mechanisms of dissolution, three ferritic steels reinforced by Y2O3 or MgO were irradiated with different charged particles. Inelastic interactions induced by 1 MeV He ion irradiation do not lead to any modification, neither in their chemical composition, nor in their spatial and size distribution. In contrast, isolated Frenkel pairs created by electron irradiation lead to significant oxide dissolution with a radius decrease proportional to the dose. Moreover, the comparison between irradiation with ions (displacements cascades) and electrons (Frenkel pairs only) shows the importance of free point defects in the dissolution phenomena. (C) 2004 Elsevier B.V. All rights reserved.
引用
收藏
页码:311 / 321
页数:11
相关论文
共 50 条
  • [11] Precipitation of Oxide Particles in Oxide Dispersion Strengthened (ODS) Ferritic Steels
    Oono, Naoko
    Ukai, Shigeharu
    MATERIALS TRANSACTIONS, 2018, 59 (10) : 1651 - 1658
  • [12] Microstructural characterization of oxide dispersion strengthened ferritic steel powder
    Pandey, Abhishek
    Palneedi, Haribabu
    Jayasankar, K.
    Parida, P.
    Debata, M.
    Mishra, B. K.
    Saroja, S.
    JOURNAL OF NUCLEAR MATERIALS, 2013, 437 (1-3) : 29 - 36
  • [13] Microstructural studies of oxide dispersion strengthened austenitic steels
    Suresh, Koppoju
    Nagini, M.
    Vijay, R.
    Ramakrishna, M.
    Gundakaram, Ravi. C.
    Reddy, A. V.
    Sundararajan, G.
    MATERIALS & DESIGN, 2016, 110 : 519 - 525
  • [14] Development of oxide dispersion strengthened ferritic steels for fusion reactors
    Mukhopadhay, DK
    Suryanarayana, C
    Froes, FH
    Hebeisen, J
    Gelles, DS
    HOT ISOSTATIC PRESSING, CONFERENCE PROCEEDINGS, 1996, : 175 - 179
  • [15] Development of oxide dispersion strengthened ferritic steels with and without aluminum
    Jae Hoon Lee
    Frontiers in Energy, 2012, 6 (1) : 29 - 34
  • [16] Tube manufacturing and characterization of oxide dispersion strengthened ferritic steels
    Ukai, S
    Mizuta, S
    Yoshitake, T
    Okuda, T
    Fujiwara, M
    Hagi, S
    Kobayashi, T
    JOURNAL OF NUCLEAR MATERIALS, 2000, 283 : 702 - 706
  • [17] Development of oxide dispersion strengthened ferritic steels with and without aluminum
    Lee, Jae Hoon
    FRONTIERS IN ENERGY, 2012, 6 (01) : 29 - 34
  • [18] Heavy-ion irradiation effects on the morphology of complex oxide particles in oxide dispersion strengthened ferritic steels
    Kishimoto, H.
    Yutani, K.
    Kasada, R.
    Hashitomi, O.
    Kimura, A.
    JOURNAL OF NUCLEAR MATERIALS, 2007, 367 : 179 - 184
  • [19] Effects of neutron irradiation on the tensile properties of high-Cr oxide dispersion strengthened ferritic steels
    Cho, H. S.
    Kasada, R.
    Kimura, A.
    JOURNAL OF NUCLEAR MATERIALS, 2007, 367 : 239 - 243
  • [20] Stability of nanoclusters in an oxide dispersion strengthened alloy under neutron irradiation
    Liu, Xiang
    Miao, Yinbin
    Wu, Yaqiao
    Maloy, Stuart A.
    Stubbins, James F.
    SCRIPTA MATERIALIA, 2017, 138 : 57 - 61