Microstructural changes in a neutron-irradiated Fe-6 at.%Cr alloy

被引：33
|
作者：
Bachhav, Mukesh [1 ]
Yao, Lan [1 ]
Odette, G. Robert [2 ]
Marquis, Emmanuelle A. [1 ]
机构：
[1] Univ Michigan, Dept Mat Sci & Engn, Ann Arbor, MI 48109 USA
[2] Univ Calif Santa Barbara, Dept Mat, Santa Barbara, CA 93106 USA
来源：
JOURNAL OF NUCLEAR MATERIALS | 2014年 / 453卷 / 1-3期
关键词：
RADIATION-INDUCED SEGREGATION; GRAIN-BOUNDARY SEGREGATION; AUSTENITIC STAINLESS-STEELS; ATOM-PROBE TOMOGRAPHY; FERRITIC/MARTENSITIC STEEL; MARTENSITIC STEELS; FERRITIC STEELS; PRECIPITATION; IRON; SOLUTE;
D O I：
10.1016/j.jnucmat.2014.06.050
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The microstructural and chemical changes in a Fe-6 at.%Cr binary model alloy neutron irradiated to 1.82 dpa at 290 degrees C were investigated using atom probe tomography. After irradiation, Si and Cr are found segregated to dislocation loops, which were analyzed in terms of number density, size, and habit plane. Grain boundary chemistry was quantitatively compared between the as-received and the neutron irradiated alloys. The results are discussed in the context of equilibrium segregation, radiation-enhanced diffusion, and/or radiation induced segregation. (C) 2014 Elsevier B.V. All rights reserved.
引用
收藏
页码：334 / 339
页数：6
相关论文
共 50 条
  • [1] Microstructural changes in a neutron-irradiated Fe-15 at.%Cr alloy
    Bachhav, Mukesh
    Odette, G. Robert
    Marquis, Emmanuelle A.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2014, 454 (1-3) : 381 - 386
  • [2] MICROSTRUCTURAL CHANGES IN NEUTRON-IRRADIATED GRAPHITE
    THROWER, PA
    REYNOLDS, WN
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1963, 8 (02) : 221 - 226
  • [3] SANS investigation of a neutron-irradiated Fe-9 at%Cr alloy
    Ulbricht, A.
    Heintze, C.
    Bergner, F.
    Eckerlebe, H.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2010, 407 (01) : 29 - 33
  • [4] MICROSTRUCTURAL EVOLUTION IN LOW-DOSE NEUTRON-IRRADIATED FE-16NI-15CR ALLOY
    HORIKI, M
    KIRITANI, M
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1994, 212 : 246 - 251
  • [5] α′ precipitation in neutron-irradiated Fe-Cr alloys
    Bachhav, Mukesh
    Odette, G. Robert
    Marquis, Emmanuelle A.
    [J]. SCRIPTA MATERIALIA, 2014, 74 : 48 - 51
  • [6] Migration of 45° [100] grain boundaries in an Fe-6 at.% Si alloy
    Lejcek, Pavel
    Havlova, Vendula
    [J]. MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2007, 462 (1-2): : 446 - 449
  • [7] Features of dislocation channeling in neutron-irradiated V-(Fe, Cr)-Ti alloy
    Fukumoto, Ken-ichi
    Sugiyama, Masanari
    Matsui, Hideki
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2007, 367 (SPEC. ISS.) : 829 - 833
  • [8] Microstructural changes and their effect on hardening in neutron irradiated Fe-Cr alloys
    Bhattacharyya, Dhriti
    Yamamoto, Takuya
    Wells, Peter
    Marquis, Emmanuelle
    Bachhav, Mukesh
    Wu, Yuan
    Davis, Joel
    Xu, Alan
    Odette, G. Robert
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2019, 519 : 274 - 286
  • [9] Effect of ambient air pressure on the oxidation kinetics of Fe-6 at.% Si alloy
    Lashin, Abdel-Rahman
    Schneeweiss, Oldrich
    Houbaert, Yvan
    [J]. CORROSION SCIENCE, 2008, 50 (09) : 2580 - 2587
  • [10] EFFECT OF ADDITIONAL MINOR ELEMENTS ON MICROSTRUCTURAL EVOLUTION OF NEUTRON-IRRADIATED FE-CR-MN ALLOYS
    TAKAHASHI, H
    OHNUKI, S
    KINOSHITA, H
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1992, 191 : 1183 - 1188
12345