Interdiffusion in uranium-zirconium solid solutions

被引:34
|
作者
Ogata, T [1 ]
Akabori, M [1 ]
Itoh, A [1 ]
Ogawa, T [1 ]
机构
[1] JAPAN ATOM ENERGY RES INST,TOKAI,IBARAKI 31911,JAPAN
关键词
D O I
10.1016/S0022-3115(96)00409-6
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Interdiffusion coefficients in the (gamma-U, beta-Zr) solid solutions have been measured in the temperature range of 973 to 1223 K and in the Zr concentration range of 0.1 to 0.95 atomic fraction. The data measured at lower temperature than 1223 K have shown notable depression in the Zr concentration range of 0.2 to 0.4 atomic fraction. The dependencies of the obtained data on alloy composition and temperature are consistent with variation of the thermodynamic factor which is calculated based on the evaluation of the activity coefficient in the U-Zr system. The interdifusion coefficient in the neighborhood of the Zr atomic fraction of 0.3 cannot be expressed by a single set of a frequency factor and an activation energy because of the significant influence of the thermodynamic factor on the interdiffusivity in the U-Zr solid solutions.
引用
收藏
页码:125 / 130
页数:6
相关论文
共 50 条
  • [31] Characterization of uranium and uranium-zirconium deposits produced in electrorefining of spent nuclear fuel
    Totemeier, TC
    ROLL OF CHARACTERIZATION IN UNDERSTANDING ENVIRONMENTAL DEGRADATION OF MATERIALS, 1998, 25 : 363 - 371
  • [33] Thermal conductivity of uranium metal and uranium-zirconium alloys fabricated via powder metallurgy
    Ortega, Luis H.
    Blamer, Brandon
    Stern, Karyn M.
    Vollmer, James
    McDeavitt, Sean M.
    JOURNAL OF NUCLEAR MATERIALS, 2020, 531
  • [34] Hydrogen Storage in the Uranium-zirconium Compounds Prepared by Powder Mettalurgy
    Deaconu, Mariea
    Ciuca, Ion
    Meleg, Tiberiu
    Mihalache, Maria
    Dinu, Alice
    REVISTA DE CHIMIE, 2016, 67 (07): : 1338 - 1344
  • [35] OXIDATION OF 50 WEIGHT PER CENT URANIUM-ZIRCONIUM ALLOY
    BARNARTT, S
    CHARLES, RG
    GULBRANSEN, EA
    JOURNAL OF THE ELECTROCHEMICAL SOCIETY, 1957, 104 (04) : 218 - 221
  • [37] Combined ab initio and empirical model of the thermal conductivity of uranium, uranium-zirconium, and uranium-molybdenum
    Zhou, Shuxiang
    Jacobs, Ryan
    Xie, Wei
    Tea, Eric
    Hin, Celine
    Morgan, Dane
    PHYSICAL REVIEW MATERIALS, 2018, 2 (08):
  • [38] Resilience of uranium mononitride/zirconium carbide composites and uranium-zirconium carbonitride in hot hydrogen for nuclear thermal propulsion
    Hamilton, Sarah R.
    Zillinger, James
    Scott, Randall
    Jerred, Nathan
    Palomares, Kelsa
    Salasin, John
    Miller, Victoria M.
    JOURNAL OF NUCLEAR MATERIALS, 2024, 596
  • [39] Comparative Analysis of Experimental Data on the Sublimation of Uranium Carbonitrides and Uranium-Zirconium Carbonitrides at High Temperatures
    Bulatov, G. S.
    German, K. E.
    RADIOCHEMISTRY, 2023, 65 (06) : 619 - 627