Nanocluster irradiation evolution in Fe-9%Cr ODS and ferritic-martensitic alloys

被引:46
作者
Swenson, M. J. [1 ]
Wharry, J. P. [2 ]
机构
[1] Boise State Univ, 1910 Univ Dr, Boise, ID 83725 USA
[2] Purdue Univ, 400 Cent Dr, W Lafayette, IN 47907 USA
关键词
Nanoclusters; Ion irradiation; Neutron irradiation; Oxide dispersion strengthened; Ferritic/martensitic; HT9; HCM12A; G-phase; Phase separation; MOLECULAR-DYNAMICS SIMULATION; DISPERSION-STRENGTHENED STEEL; ION-IRRADIATION; PHASE-STABILITY; DISPLACEMENT CASCADES; MECHANICAL-PROPERTIES; STRUCTURAL-MATERIALS; MATERIALS CHALLENGES; NEUTRON-IRRADIATION; RADIATION RESPONSE;
D O I
10.1016/j.jnucmat.2017.08.045
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The objective of this study is to evaluate the influence of dose rate and cascade morphology on nanocluster evolution in a model Fe-9%Cr oxide dispersion strengthened steel and the commercial ferritic/ martensitic (F/M) alloys HCM12A and HT9. We present a large, systematic data set spanning the three alloys, three irradiating particle types, four orders of magnitude in dose rate, and doses ranging 1-100 displacements per atom over 400-500 degrees C. Nanoclusters are characterized using atom probe tomography. ODS oxide nanoclusters experience partial dissolution after irradiation due to inverse Ostwald ripening, while F/M nanoclusters undergo Ostwald ripening. Damage cascade morphology is indicative of nanocluster number density evolution. Finally, the effects of dose rate on nanocluster morphology provide evidence for a temperature dilation theory, which purports that a negative temperature shift is necessary for higher dose rate irradiations to emulate nanocluster evolution in lower dose rate irradiations. (C) 2017 Elsevier B. V. All rights reserved.
引用
收藏
页码:24 / 40
页数:17
相关论文
共 91 条
  • [1] Allen T., 2012, ATR NATL SCI USER FA
  • [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] Materials challenges for nuclear systems
    Allen, Todd
    Busby, Jeremy
    Meyer, Mitch
    Petti, David
    [J]. MATERIALS TODAY, 2010, 13 (12) : 14 - 23
  • [4] Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature
    Allen, Todd R.
    Kaoumi, Djamel
    Wharry, Janelle P.
    Jiao, Zhijie
    Topbasi, Cem
    Kohnert, Aaron
    Barnard, Leland
    Certain, Alicia
    Field, Kevin G.
    Was, Gary S.
    Morgan, Dane L.
    Motta, Arthur T.
    Wirth, Brian D.
    Yang, Y.
    [J]. JOURNAL OF MATERIALS RESEARCH, 2015, 30 (09) : 1246 - 1274
  • [5] The stability of 9Cr-ODS oxide particles under heavy-ion irradiation
    Allen, TR
    Gan, J
    Cole, JI
    Ukai, S
    Shutthanandan, S
    Thevuthasan, S
    [J]. NUCLEAR SCIENCE AND ENGINEERING, 2005, 151 (03) : 305 - 312
  • [6] Phase stability of an HT-9 duct irradiated in FFTF
    Anderoglu, O.
    Van den Bosch, J.
    Hosemann, P.
    Stergar, E.
    Sencer, B. H.
    Bhattacharyya, D.
    Dickerson, R.
    Dickerson, P.
    Hartl, M.
    Maloy, S. A.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2012, 430 (1-3) : 194 - 204
  • [7] [Anonymous], 2001, HIGH CHROMIUM FERRIT
  • [8] ION-IRRADIATION STUDIES OF THE DAMAGE FUNCTION OF COPPER AND SILVER
    AVERBACK, RS
    BENEDEK, R
    MERKLE, KL
    [J]. PHYSICAL REVIEW B, 1978, 18 (08): : 4156 - 4171
  • [9] ATOMIC DISPLACEMENT PROCESSES IN IRRADIATED METALS
    AVERBACK, RS
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1994, 216 : 49 - 62
  • [10] α′ precipitation in neutron-irradiated Fe-Cr alloys
    Bachhav, Mukesh
    Odette, G. Robert
    Marquis, Emmanuelle A.
    [J]. SCRIPTA MATERIALIA, 2014, 74 : 48 - 51