INERT-ATMOSPHERE HOT CELLS FOR EXAMINATION OF IRRADIATED U-PU FUEL-ELEMENTS

被引：0
|
作者：
MASON, PA
MONTGOME.CD
FRANTZ, CE
机构：
来源：
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1971年 / 14卷 / 02期
关键词：
D O I：
暂无
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：
引用
收藏
页码：871 / &
相关论文
共 12 条
  • [1] PNEUMATIC TRANSFER SYSTEM FOR INERT-ATMOSPHERE HOT CELLS
    MCCLURKIN, JL
    TOBIAS, DA
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 22 (NOV16): : 747 - 747
  • [2] EXAMINATION TECHNIQUES FOR HIGH BURNUP U-PU FUEL ELEMENTS FOR FAST-BREEDER REACTORS
    KOPROWSK.BJ
    BROWN, FL
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1967, 10 (02): : 671 - &
  • [3] A NEW PROCESSING SYSTEM AND METHOD FOR EXAMINATION OF IRRADIATED FUEL-ELEMENTS
    CHEN, YN
    CHUANG, YD
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1983, 44 : 487 - 488
  • [4] EDDY-CURRENT EXAMINATION OF IRRADIATED FUEL-ELEMENTS AT HFEF
    PHIPPS, RD
    KLEISS, RE
    COUGHLAN, JB
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1977, 27 (NOV): : 1003 - 1004
  • [5] THERMAL AND FAST IRRADIATION OF SODIUM-BONDED (U,PU)C FUEL AND FUEL-ELEMENTS
    CLIFFORD, JC
    CUBITT, RL
    BARNER, JO
    KIRKPATRICK, DC
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1971, 14 (NAPR): : 39 - +
  • [6] MOLTEN-SALTS USE FOR U-PU RECOVERY FROM IRRADIATED FUEL OR FROM COMBUSTIBLE WASTES
    BRAMBILLA, G
    FACCHINI, AG
    ABSTRACTS OF PAPERS OF THE AMERICAN CHEMICAL SOCIETY, 1983, 185 (MAR): : 93 - NUCL
  • [7] MEASUREMENTS TO DISTINGUISH FUEL-ELEMENTS WITH AND WITHOUT THORIUM CONTENT BY GAMMASPECTROMETRY IN HOT CELLS
    DUWE, R
    KUHNLEIN, W
    SCHRODER, R
    NUCLEAR ENGINEERING AND DESIGN, 1994, 147 (01) : 101 - 104
  • [8] AN ELECTROANALYTICAL EXAMINATION OF THE GAS RETENTION IN A RAMPED (U,PU)O2 IRRADIATED FUEL
    BOTTOMLEY, PDW
    DAGUZANLEMOINE, F
    INSTITUTE OF PHYSICS CONFERENCE SERIES, 1993, (130): : 243 - 246
  • [9] HYPERSTOICHIOMETRIC REGIONS AS POTENTIAL SHORT-CIRCUIT PATHS FOR OXYGEN DIFFUSION IN UNRESTRUCTURED REGIONS OF IRRADIATED UO2 AND (U,PU)O2 NUCLEAR FUEL-ELEMENTS
    BRANDT, WW
    SEILS, CA
    JOHNSON, CE
    JOURNAL OF NUCLEAR MATERIALS, 1975, 57 (02) : 212 - 220
  • [10] A NON-DESTRUCTIVE METHOD OF DETERMINING THE PU/U RATIO IN FAST-REACTOR FUEL-ELEMENTS, BASED ON X-RAY SPECTROMETRY
    BUSHUEV, AV
    GALKOV, VI
    ZBONAREV, AV
    ZOLOTOV, AF
    KUTUZOV, AA
    MELNICHENKO, NA
    OZERKOV, VN
    CHACHIN, VV
    SOVIET ATOMIC ENERGY, 1982, 53 (05): : 776 - 778
12