TEM characterisation of heavy-ion irradiation damage in FeCr alloys

被引:43
作者
Xu, S. [1 ]
Yao, Z. [1 ]
Jenkins, M. L. [1 ]
机构
[1] Univ Oxford, Dept Mat, Oxford OX1 3PH, England
基金
英国工程与自然科学研究理事会;
关键词
NEUTRON-IRRADIATION; FERRITIC STEELS; CR ALLOYS; IRONS; DPA;
D O I
10.1016/j.jnucmat.2008.12.078
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Heavy-ion damage in a series of FeCr binary alloys and pure Fe has been investigated by TEM. Specimens were irradiated in bulk with 1.5 MeV Fe+ ions at an irradiation temperature of 300 degrees C. A TEM specimen preparation technique has been developed to access the peak of the buried damage region. The damage took the form of dislocation loops with sizes ranging up to a few tens of nanometres. Loops with Burgers vectors of type b = < 100 > and b = 1/2 < 111 > were both present in all the specimens, but the proportion of < 100 > loops was higher in FeCr alloys than in pure Fe. In Fe-8%Cr the loop number density was determined to be (1.6 +/- 0.2) x 1021 m-2. Nature determinations showed that < 100 > loops in Fe-11Cr and 1/2 < 111 > loops in Fe-8Cr were of interstitial type. (C) 2009 Elsevier B.V. All rights reserved.
引用
收藏
页码:161 / 164
页数:4
相关论文
共 50 条
  • [21] Characterization of Vacancy Defects Using TEM in Heavy-Ion-Irradiated Tungsten Foils
    Sharma, Prashant
    Maya, P. N.
    Satyaprasad, A.
    Deshpande, S. P.
    METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 2024, 55 (08): : 2932 - 2939
  • [22] Experimental study and numerical modelling of the irradiation damage recovery in zirconium alloys
    Ribis, J.
    Onimus, F.
    Bechade, J. -L.
    Doriot, S.
    Barbu, A.
    Cappelaere, C.
    Lemaignan, C.
    JOURNAL OF NUCLEAR MATERIALS, 2010, 403 (1-3) : 135 - 146
  • [23] Damage calculation in compound materials under neutron and ion irradiation
    Vladimirov, PV
    Lizunov, YD
    RADIATION EFFECTS AND DEFECTS IN SOLIDS, 1996, 139 (02): : 109 - 123
  • [24] Evolution of irradiation defects in Ti2AlC ceramics during heavy ion irradiation
    Wang, Fei
    Su, Qing
    Nastasi, Michael
    Kirk, Marquis A.
    Li, Meimei
    Cui, Bai
    CERAMICS INTERNATIONAL, 2018, 44 (12) : 14686 - 14692
  • [25] Characterisation of radiation damage in W and W-based alloys from 2 MeV self-ion near-bulk implantations
    Yi, Xiaoou
    Jenkins, Michael L.
    Hattar, Khalid
    Edmondson, Philip D.
    Roberts, Steve G.
    ACTA MATERIALIA, 2015, 92 : 163 - 177
  • [26] TEM Investigation on the Dislocation Loops in Zirconium Alloy by Neutron and Kr+ Ion Irradiation Tests
    Wang, Zhen
    Fang, Zhong-Qiang
    Yan, Qing-Xue
    Wu, Lu
    Lu, Chen-Yang
    MICROSCOPY AND MICROANALYSIS, 2024, 30 (01) : 59 - 65
  • [27] Dual ion irradiation of commercial and advanced alloys: Evaluating microstructural resistance for high dose core internals
    Lear, C. R.
    Song, M.
    Wang, M.
    Was, G. S.
    JOURNAL OF NUCLEAR MATERIALS, 2019, 516 : 125 - 134
  • [28] In situ study of defect accumulation in zirconium under heavy ion irradiation
    Idrees, Y.
    Yao, Z.
    Kirk, M. A.
    Daymond, M. R.
    JOURNAL OF NUCLEAR MATERIALS, 2013, 433 (1-3) : 95 - 107
  • [29] EFFECTS OF ION IRRADIATION ON MICROSTRUCTURE AND PROPERTIES OF ZIRCONIUM ALLOYS-A REVIEW
    Yan, Chunguang
    Wang, Rongshan
    Wang, Yanli
    Wang, Xitao
    Bai, Guanghai
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2015, 47 (03) : 323 - 331
  • [30] Effect of Re segregation on irradiation damage behavior of Mo-Re alloys
    Wang, Jing
    Han, Chenxu
    Zong, Hongxiang
    Ding, Xiangdong
    Sun, Jun
    COMPUTATIONAL MATERIALS SCIENCE, 2025, 250