Model for predicting the evolution of pore size distributions in UO2 fuel

被引:0
|
作者
机构
[1] Bouguerra, Y.
[2] Si-Ahmed, A.
来源
Bouguerra, Y. | 1600年 / 178期
关键词
Dollins and Nichols Pore Size Distribution Model - In Reactor Pore Shrinkage Densification - Thermal Densification Formula;
D O I
暂无
中图分类号
学科分类号
摘要
引用
收藏
页码:2 / 3
相关论文
共 50 条
  • [21] Modelling of pore coarsening in the high burn-up structure of UO2 fuel
    Veshchunov, M. S.
    Tarasov, V. I.
    JOURNAL OF NUCLEAR MATERIALS, 2017, 488 : 191 - 195
  • [22] Behaviour of MOX fuel as compared to UO2 fuel
    Guérin, Y
    Lespiaux, D
    Struzik, C
    Caillot, L
    PROCEEDINGS OF THE WORKSHOP ON THE PHYSICS AND FUEL PERFORMANCE OF REACTOR-BASED PLUTONIUM DISPOSITION, 1999, : 151 - 157
  • [23] 1ST-GENERATION MODEL TO PREDICT PARTICLE-SIZE DISTRIBUTIONS FOR CONDENSED UO2 VAPOR
    KENNEDY, MF
    ERDMAN, CA
    GARNER, PL
    REYNOLDS, AB
    WALTAR, AE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1977, 26 : 339 - 340
  • [24] A COMPREHENSIVE MODEL OF FISSION-GAS BEHAVIOR IN UO2 FUEL
    VILLALOBOS, A
    OKRENT, D
    WAZZAN, AR
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1982, 41 : 250 - 251
  • [25] An advanced model for intragranular bubble diffusivity in irradiated UO2 fuel
    Veshchunov, M. S.
    Shestak, V. E.
    JOURNAL OF NUCLEAR MATERIALS, 2008, 376 (02) : 174 - 180
  • [26] MECHANISMS OF LEACHING AND DISSOLUTION OF UO2 FUEL
    JOHNSON, LH
    SHOESMITH, DW
    LUNANSKY, GE
    BAILEY, MG
    TREMAINE, PR
    NUCLEAR TECHNOLOGY, 1982, 56 (02) : 238 - 253
  • [27] ENGINEERING FOR FISSION GAS IN UO2 FUEL
    LEWIS, WB
    NUCLEAR APPLICATIONS, 1966, 2 (02): : 171 - &
  • [28] TEMPERATURE DISTRIBUTION IN UO2 FUEL ELEMENTS
    ROBERTSON, JAL
    ROSS, AM
    NOTLEY, MJF
    MACEWAN, JR
    JOURNAL OF NUCLEAR MATERIALS, 1962, 7 (03) : 225 - 262
  • [29] VOLUME CHANGES IN IRRADIATED UO2 FUEL
    HASTINGS, IJ
    ROSE, DH
    SCHANKULA, MH
    JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1975, 58 (1-2) : 74 - 74
  • [30] ECONOMICS OF UO2 FUEL FOR RESEARCH REACTORS
    LUMB, RF
    MACPHEE, J
    NUCLEAR APPLICATIONS, 1967, 3 (03): : 157 - &