The influence of americium oxide inclusions on the thermal conductivity of inert-matrix fuel

被引：4
|
作者：
Bakker, K [1 ]
Konings, RJM [1 ]
机构：
[1] Netherlands Energy Res Fdn, ECN, NL-1755 ZG Petten, Netherlands
来源：
JOURNAL OF ALLOYS AND COMPOUNDS | 1998年 / 271卷
关键词：
thermal conductivity; americium; transmutation; CERCER;
D O I：
10.1016/S0925-8388(98)00175-3
中图分类号：
O64 [物理化学（理论化学）、化学物理学];
学科分类号：
070304 ; 081704 ;
摘要：
The thermal conductivities of heterogeneous mixtures of americium oxides and inert-matrix materials are computed. In the case of americium-oxide inclusions with a random shape the Finite Element Method (FEM) has been used and in the case of inclusions with a spherical shape an analytical equation has been used. The influence of fission product-induced damage to the inert matrix on the temperature distribution and on the overall thermal conductivity has been modelled for various sizes of the fissile particles. (C) 1998 Elsevier Science S.A.
引用
收藏
页码：632 / 635
页数：4
相关论文
共 50 条
  • [1] On the thermal conductivity of inert-matrix fuels containing americium oxide
    Bakker, K
    Konings, RJM
    JOURNAL OF NUCLEAR MATERIALS, 1998, 254 (2-3) : 129 - 134
  • [2] Silicon carbide as an inert-matrix for a thermal reactor fuel
    Verrall, R.A.
    Vlajic, M.D.
    Krstic, V.D.
    Journal of Nuclear Materials, 1999, 274 (01): : 54 - 60
  • [3] Silicon carbide as an inert-matrix for a thermal reactor fuel
    Verrall, RA
    Vlajic, MD
    Krstic, VD
    JOURNAL OF NUCLEAR MATERIALS, 1999, 274 (1-2) : 54 - 60
  • [4] Feasibility of partial LWR core loadings with inert-matrix fuel
    Kasemeyer, U
    Hellwig, C
    Dean, DW
    Chawla, R
    Meier, G
    Williams, T
    ADVANCED REACTORS WITH INNOVATIVE FUELS, WORKSHOP PROCEEDINGS, 2002, : 245 - 260
  • [5] The irradiation test of Inert-Matrix Fuel in comparison to uranium plutonium mixed oxide fuel at the Halden Reactor
    Kasemeyer, U
    Hellwig, C
    Lee, YW
    Ledergerber, G
    Sohn, DS
    Gates, GA
    Wiesenack, W
    PROGRESS IN NUCLEAR ENERGY, 2001, 38 (3-4) : 309 - 312
  • [6] Numerical analysis of effective thermal conductivity associated with microstructural changes of porous SiC as an inert-matrix
    Jung, J.H.
    Krstic, V.D.
    Cho, H.K.
    Metals and Materials International, 2001, 7 (01): : 21 - 26
  • [7] Numerical analysis of effective thermal conductivity associated with microstructural changes of porous SiC as an inert-matrix
    J. H. Jung
    V. D. Krstic
    H. K. Cho
    Metals and Materials International, 2001, 7 : 21 - 26
  • [8] Numerical analysis of effective thermal conductivity associated with microstructural changes of porous SiC as an inert-matrix
    Jung, JH
    Krstic, VD
    Cho, HK
    METALS AND MATERIALS-KOREA, 2001, 7 (01): : 21 - 26
  • [9] Optimization of inert matrix fuel concepts for americium transmutation
    Chauvin, N.
    Konings, R.J.M.
    Matzke, Hj.
    Journal of Nuclear Materials, 1999, 274 (01): : 105 - 111
  • [10] Optimisation of inert matrix fuel concepts for americium transmutation
    Chauvin, N
    Konings, RJM
    Matzke, H
    JOURNAL OF NUCLEAR MATERIALS, 1999, 274 (1-2) : 105 - 111
12345