Radiation resistance of high-density uranium—molybdenum dispersion fuel for nuclear research reactors

被引：0
|
作者：
A. V. Vatulin
A. V. Morozov
V. B. Suprun
Yu. I. Petrov
Yu. I. Trifonov
机构：
[1] A. A. Bochvar All-Russia Research Institute of Standardization in Machine Engineering,
来源：
Atomic Energy | 2006年 / 100卷
关键词：
Uranium; Molybdenum; Matrix Material; Irradiation Condition; Fuel Element;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
The results of radiation tests are discussed and the character of the failure of fuel compositions and the operability of fuel elements is analyzed as a function of the type of fuel and the irradiation conditions. The intense interaction of the fuel with the matrix material is considered as the main factor limiting the operability of fuel elements in power-dense high-flux nuclear reasearch reactors. It is concluded that low-enrichment high-density uranium—molybdenym fuel can provide reliable operation of dispersion fuel elements in low-and medium-power research reactors. Such fuel can be used in power-dense high-flux research reactors if the fuel load is decreased below the maximum admissible amount, the compatibility of the uranium—molybdenum alloy with an aluminum matrix is radically improved, or fuel elements with a different construction, for example, monolithic, are used.
引用
收藏
页码：37 / 46
页数：9
相关论文
共 50 条
  • [1] Radiation resistance of high-density uranium-molybdenum dispersion fuel for nuclear research reactors
    Vatulin, AV
    Morozov, AV
    Suprun, VB
    Petrov, YI
    Trifonov, YI
    ATOMIC ENERGY, 2006, 100 (01) : 37 - 46
  • [2] High-density, low-enriched uranium fuel for nuclear research reactors
    D. D. Keiser
    S. L. Hayes
    M. K. Meyer
    C. R. Clark
    JOM, 2003, 55 : 55 - 58
  • [3] High-density, low-enriched uranium fuel for nuclear research reactors
    Keiser, DD
    Hayes, SL
    Meyer, MK
    Clark, CR
    JOM-JOURNAL OF THE MINERALS METALS & MATERIALS SOCIETY, 2003, 55 (09): : 55 - 58
  • [4] Development Of High Density Uranium Compounds And Alloys As Dispersion Fuel For Research And Test Reactors
    Sinha, V. P.
    Hegde, P. V.
    Prasad, G. J.
    Mishra, G. P.
    Pal, S.
    TRANSACTIONS OF THE INDIAN INSTITUTE OF METALS, 2008, 61 (2-3) : 115 - 120
  • [5] Development of high density uranium compounds and alloys as dispersion fuel for research and test reactors
    V. P. Sinha
    P. V. Hegde
    G. J. Prasad
    G. P. Mishra
    S. Pal
    Transactions of the Indian Institute of Metals, 2008, 61 : 115 - 120
  • [6] Development of FA with High-Density Fuel for Foreign Research Nuclear Reactors of Russian Design
    Yu. S. Cherepnin
    A. A. Pulinets
    O. A. Kravtsova
    A. R. Simonidi
    E. S. Chizhova
    I. A. Larionov
    S. I. Logvenchev
    Atomic Energy, 2021, 129 : 234 - 236
  • [7] Development of FA with High-Density Fuel for Foreign Research Nuclear Reactors of Russian Design
    Cherepnin, Yu. S.
    Pulinets, A. A.
    Kravtsova, O. A.
    Simonidi, A. R.
    Chizhova, E. S.
    Larionov, I. A.
    Logvenchev, S. I.
    ATOMIC ENERGY, 2021, 129 (04) : 234 - 236
  • [8] High-density U-Mo fuel for research reactors
    A. V Vatulin
    A. V. Morozov
    V. B. Suprun
    Yu. I. Petrov
    Yu. I. Trifonov
    Metal Science and Heat Treatment, 2004, 46 : 484 - 489
  • [9] DEVELOPMENT OF A HIGH-URANIUM-DENSITY FUEL FOR RESEARCH AND TEST REACTORS
    STAHL, D
    DOMAGALA, RF
    THRESH, HR
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 33 (NOV): : 745 - 745
  • [10] Effect of high-density fuel loading on criticality of low enriched uranium fueled material test research reactors
    Ahmed, R
    Aslam
    Ahmad, N
    ANNALS OF NUCLEAR ENERGY, 2005, 32 (01) : 29 - 62
12345