Analysis of the effect of the energy of interatomic interaction and the structure of Fe-Cr alloys on the processes of radiation-induced segregation after ion etching

被引：0
|
作者：
G. V. Lysova
G. A. Birzhevoy
M. I. Zakharova
N. P. Solov’ev
机构：
[1] Physical and Power Engineering Institute,Leipunsky State Scientific Center of the Russian Federation
来源：
Journal of Surface Investigation. X-ray, Synchrotron and Neutron Techniques | 2008年 / 2卷
关键词：
Surface Investigation; Neutron Technique; Interstitial Atom; Interatomic Interaction; Chromium Atom;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
We present the results of a comparative analysis of profiles of the radiation-induced segregation of chromium after irradiation of model alloys Fe-(9, 11, 14) at % Cr by He+ ions with the energy of 30 keV with fluences 1019–1021 ions/m2 at 450°C and data on varying the moduli of normal elasticity and the structure of these alloys depending on the Cr concentration. It is shown that an interstitial migration mechanism is the determining factor in the case of chromium segregation near the surface. A correlation between the character of varying the elasticity moduli, order, and value of surface segregation and swelling of the Fe-Cr alloys depending on the Cr concentration is established.
引用
收藏
页码：178 / 183
页数：5
相关论文
共 42 条
  • [21] Radiation induced segregation near dislocations and symmetric tilt grain boundaries in Fe-Cr alloys: A phase-field study
    Moladje, G.F. Bouobda
    Thuinet, L.
    Becquart, C.S.
    Legris, A.
    Acta Materialia, 2022, 225
  • [22] Radiation induced segregation near dislocations and symmetric tilt grain boundaries in Fe-Cr alloys: A phase-field study
    Moladje, G. F. Bouobda
    Thuinet, L.
    Becquart, C. S.
    Legris, A.
    ACTA MATERIALIA, 2022, 225
  • [23] Modeling solute-vacancy trapping at oversized solutes and its effect on radiation-induced segregation in Fe-Cr-Ni alloys
    Hackett, M. J.
    Najafabadi, R.
    Was, G. S.
    JOURNAL OF NUCLEAR MATERIALS, 2009, 389 (02) : 279 - 287
  • [24] Ab-initio based modeling of diffusion in dilute bcc Fe-Ni and Fe-Cr alloys and implications for radiation induced segregation
    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
  • [25] Radiation-induced segregation in FE-CR-NI alloy by electron/helium ion dual beam irradiation
    1600,
  • [26] Effect of grain boundary orientation on radiation-induced segregation in a Fe-15.2 at.% Cr alloy
    Hu, Rong
    Smith, George D. W.
    Marquis, Emmanuelle A.
    ACTA MATERIALIA, 2013, 61 (09) : 3490 - 3498
  • [27] Relationships between depth-resolved primary radiation damage, irradiation-induced nanostructure and nanoindentation response of ion-irradiated Fe-Cr and ODS Fe-Cr alloys
    Vogel, K.
    Heintze, C.
    Chekhonin, P.
    Akhmadaliev, S.
    Altstadt, E.
    Bergner, F.
    NUCLEAR MATERIALS AND ENERGY, 2020, 24
  • [28] Nanoindentation Response of Ion-Irradiated Fe, Fe-Cr Alloys and Ferritic-Martensitic Steel Eurofer 97: The Effect of Ion Energy
    Das, Aniruddh
    Altstadt, Eberhard
    Kaden, Cornelia
    Kapoor, Garima
    Akhmadaliev, Shavkat
    Bergner, Frank
    FRONTIERS IN MATERIALS, 2022, 8 (08):
  • [29] Atomistic simulation of the segregation of alloying elements close to radiation-induced defects in irradiated Fe–Cr–Ni BCC alloys
    Bakaev A.V.
    Terentyev D.A.
    Zhurkin E.E.
    Journal of Surface Investigation: X-ray, Synchrotron and Neutron Techniques, 2017, 11 (3) : 606 - 613
  • [30] Radiation-induced segregation at grain boundary in Fe-Cr-Ni alloy system: Effect of temperature variation
    Watanabe, S
    Satou, J
    Sakaguchi, N
    Takahashi, H
    Namba, C
    JOURNAL OF NUCLEAR MATERIALS, 1996, 239 (1-3) : 200 - 204
12345