TESTING SEALING OF FUEL-RODS CONTAINING MATRIX FUEL IN RELOADING A POWER-REACTOR

被引:0
|
作者
ZHEMZHUROV, ML
LEVADNYI, VA
BURNOS, VV
机构
关键词
D O I
10.1007/BF00761257
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
[No abstract available]
引用
收藏
页码:280 / 282
页数:3
相关论文
共 50 条
  • [31] WATERSIDE CORROSION PERFORMANCE OF LIGHT WATER POWER-REACTOR FUEL
    GARZAROLLI, F
    HOLZER, R
    NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1992, 31 (01): : 65 - 85
  • [32] STEADY-STATE IRRADIATION AND RAMP TESTING OF HIGHLY INSTRUMENTED FUEL-RODS
    RUYTER, I
    POTT, G
    MARKGRAF, J
    SONTHEIMER, F
    RES MECHANICA, 1985, 16 (02): : 117 - 134
  • [33] MODEL FOR CALCULATING NUCLEAR FUEL CYCLE OF ONE POWER-REACTOR
    MULLER, A
    KERNENERGIE, 1973, 16 (09): : 270 - 273
  • [34] HOT CELL EXAMINATION TECHNIQUES FOR THE POWER-REACTOR FUEL ASSEMBLY
    SAKAKURA, A
    YAMAKI, J
    IWAMOTO, K
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1982, 43 : 729 - 729
  • [35] ELECTROREDOX PROCEDURES FOR PLUTONIUM IN POWER-REACTOR FUEL-REPROCESSING
    BAUMGARTNER, F
    GOLDACKER, H
    SCHMIEDER, H
    ABSTRACTS OF PAPERS OF THE AMERICAN CHEMICAL SOCIETY, 1979, (APR): : 29 - 29
  • [38] Prospective Power-Reactor Fuel Cycles Based on Water-Free Reprocessing of Spent Fuel
    A. F. Grachev
    A. A. Maershin
    O. V. Skiba
    V. A. Tsykanov
    A. V. Bychkov
    M. V. Kormilitsyn
    Yu. S. Sokolovskii
    Atomic Energy, 2004, 96 : 320 - 326
  • [39] Prospective power-reactor fuel cycles based on water-free reprocessing of spent fuel
    Grachev, AF
    Maershin, AA
    Skiba, OV
    Tsykanov, VA
    Bychkov, AV
    Kormilitsyn, MV
    Sokolovskii, YS
    ATOMIC ENERGY, 2004, 96 (05) : 320 - 326
  • [40] A MATHEMATICAL-MODEL FOR INVESTIGATION OF THE REWETTING OF FUEL-RODS
    SCHUTZLE, R
    UNGER, H
    NUCLEAR ENGINEERING AND DESIGN, 1987, 101 (03) : 315 - 322