Microstructural anomalies in hot-isostatic pressed U-10 wt.% Mo fuel plates with Zr diffusion barrier

被引:18
作者
Park, Y. [1 ]
Eriksson, N. [1 ]
Keiser, D. D., Jr. [2 ]
Jue, J. F. [2 ]
Rabin, B. [2 ]
Moore, G. [2 ]
Sohn, Y. H. [1 ]
机构
[1] Univ Cent Florida, Dept Mat Sci & Engn, Adv Mat Proc & Anal Ctr, Orlando, FL 32816 USA
[2] Idaho Natl Lab, Idaho Falls, ID 83401 USA
关键词
Uranium alloy; Zirconium; Microstructure; Transmission electron microscopy; DISPERSION FUEL; HIGH-DENSITY; URANIUM; ALLOY; MATRIX;
D O I
10.1016/j.matchar.2015.03.015
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Microstructural anomalies in the co-rolled-and-HIP'ed U-10 wt.% Mo (U10Mo) metallic fuel plate with Zr diffusion barrier assembly were examined as a function of HIP temperature (from 520 to 580 degrees C) and duration (45, 60, 90, 180 and 345 min) by scanning and transmission electron microscopy. The anomalies observed in this study are carbide/oxide inclusions within the U10Mo fuel alloy, and regions of limited interaction between the U10Mo alloy and Zr barrier, frequently associated with carbide/oxide inclusions. In the U10Mo alloy, the cF8, Fm3m (225) UC phase (a = 4.955 angstrom) and cF12, Fm3m (225) UO2 phase (a = 5.467 angstrom) were observed throughout the U10Mo alloy with an approximate volume percent of 0.5 to 1.8. The volume percent of the UC-UO2 inclusions within the U10Mo alloy did not change as functions of HIP temperature and time. These inclusion phases, located near the surface of the U10Mo alloy, were frequently observed to impede the development of interdiffusion and reaction between the U10Mo alloy and Zr diffusion barrier. The regions of limited interaction between the U10Mo and Zr barrier decreased with an increase in HIP temperature, however no noticeable trend was observed with an increase in HIP duration at constant temperature of 560 degrees C. (C) 2015 Elsevier Inc. All rights reserved.
引用
收藏
页码:50 / 57
页数:8
相关论文
共 37 条
  • [1] [Anonymous], PHYS METALLUGY URANI
  • [2] Beghi G., 1968, Gamma Phase Uranium-Molybdenum Fuel Alloys
  • [3] Belle J., 1981, URANIUM DIOXIDE PROP
  • [4] Burkes D.E., 2010, THERMOPHYSICAL PROPE
  • [5] Properties of DU-10 wt% Mo alloys subjected to various post-rolling heat treatments
    Burkes, Douglas E.
    Prabhakaran, Ramprashad
    Hartmann, Thomas
    Jue, Jan-Fong
    Rice, Francine J.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (06) : 1332 - 1339
  • [6] THE CARBIDES OF URANIUM
    FROST, BRT
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1963, 10 (04) : 265 - 300
  • [7] Halden F.A., 1959, SRITDI5722
  • [8] Hoge K., 1966, J BASIC ENG, V6, P509
  • [9] Interdiffusion Between Zr Diffusion Barrier and U-Mo Alloy
    Huang, K.
    Park, Y.
    Keiser, D. D., Jr.
    Sohn, Y. H.
    [J]. JOURNAL OF PHASE EQUILIBRIA AND DIFFUSION, 2012, 33 (06) : 443 - 449
  • [10] Microstructural characteristics of HIP-bonded monolithic nuclear fuels with a diffusion barrier
    Jue, Jan-Fong
    Keiser, Dennis D., Jr.
    Breckenridge, Cynthia R.
    Moore, Glenn A.
    Meyer, Mitchell K.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2014, 448 (1-3) : 250 - 258