Microstructural examination of zirconium alloys following in-pile creep testing in the HALDEN reactor

被引:1
|
作者
Anderson, Ken R. [1 ]
Karlsen, Wade [2 ]
Ivanchenko, Mykola [2 ]
Carter, Jesse J. [1 ]
Smith, Richard W. [1 ]
机构
[1] Naval Nucl Lab, West Mifflin, PA 15122 USA
[2] VTT Tech Res Ctr, Kemistintie 3, Espoo, Finland
基金
芬兰科学院;
关键词
Zircaloy-2; Neutron-irradiated; Microstructure; In-pile creep; Rate-theory; DOSE NEUTRON-IRRADIATION; RATE DEPENDENCE; PRODUCTION BIAS; ATOM-PROBE; EVOLUTION; RADIATION; ZIRCALOY-2; DAMAGE; REDISTRIBUTION; BEHAVIOR;
D O I
10.1016/j.jnucmat.2018.11.013
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Post-irradiation examination (PIE) in the form of transmission electron microscopy (TEM) was used to characterize the microstructure of several specimens of Zircaloy-2 and Zircaloy-2 plus 1% Nb that had previously underwent in-pile creep testing in the HALDEN reactor. The purpose of the examination was to explore a microstructural basis for an apparent substantially increased rate of hardening over that observed with similar materials in the higher fast-flux environments of the ATR or HFIR, and to investigate the increased creep strength exhibited by the Nb-containing alloy relative to pure Zircaloy-2. The analysis of irradiation-induced defects indicated a higher than expected density, which was consistent with the observed high hardening rate. Modeling based on mean field rate theory suggests the lower neutron flux in the HALDEN reactor results in a higher fraction of irradiation-induced defects being available for sink (loop) nucleation and growth. (C) 2018 Elsevier B.V. All rights reserved.
引用
收藏
页码:260 / 270
页数:11
相关论文
共 28 条
  • [1] In situ monitored in-pile creep testing of zirconium alloys
    Kozar, R. W.
    Jaworski, A. W.
    Webb, T. W.
    Smith, R. W.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2014, 444 (1-3) : 14 - 22
  • [2] In-Pile Testing of CrN, TiAlN, and AlCrN Coatings on Zircaloy Cladding in the Halden Reactor
    Van Nieuwenhove, Rudi
    Andersson, Vendi
    Balak, Juraj
    Oberlander, Barbara
    [J]. ZIRCONIUM IN THE NUCLEAR INDUSTRY: 18TH INTERNATIONAL SYMPOSIUM, 2018, 1597 : 965 - 982
  • [3] IN-PILE PERFORMANCE OF HANA CLADDING TESTED IN HALDEN REACTOR
    Kim, Hyun-Gil
    Park, Jeong-Yong
    Jeong, Yong-Hwan
    Koo, Yang-Hyun
    Yoo, Jong-Sung
    Mok, Yong-Kyoon
    Kim, Yoon-Ho
    Suh, Jung-Min
    [J]. NUCLEAR ENGINEERING AND TECHNOLOGY, 2014, 46 (03) : 423 - 430
  • [4] The mechanism of localized in-pile corrosion of zirconium alloys
    Ozaki, S
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1998, 35 (09) : 654 - 661
  • [5] Rod overpressure/lift-off testing at Halden -: In-pile data and analysis
    Wiesenack, Wolfgang
    Tverberg, Terje
    Mcgrath, Margaret
    Kolstad, Erik
    Beguin, Stephan
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2006, 43 (09) : 1037 - 1044
  • [6] The mechanism of localized in-pile corrosion of zirconium alloys, (II)
    Ozaki, S
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1999, 36 (07) : 605 - 612
  • [7] The mechanism of localized in-pile corrosion of zirconium alloys, (III)
    Ozaki, S
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1999, 36 (09) : 792 - 797
  • [8] ANISOTHERMAL EFFECTS DURING IN-PILE CREEP TESTING OF URANIUM DIOXIDE
    WILSON, WRD
    PERRIN, JS
    [J]. NUCLEAR SCIENCE AND ENGINEERING, 1971, 45 (01) : 99 - &
  • [9] IN-PILE DIMENSIONAL CHANGES IN NEUTRON-IRRADIATED ZIRCONIUM BASE ALLOYS
    DOLLINS, CC
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1976, 59 (01) : 61 - 76
  • [10] UNIAXIAL IN-REACTOR CREEP OF ZIRCONIUM ALLOYS
    FIDLERIS, V
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1968, 26 (01) : 51 - &