DESIGN, FABRICATION AND PREOPERATIONAL TESTING OF A TRANSPORTABLE VOLUME REDUCTION AND SOLIDIFICATION SYSTEM

被引:0
|
作者
JESSOP, DT
SNOW, AL
机构
[1] ADV TECHNOL INC, CHARLOTTE, NC 28281 USA
[2] DUKE POWER CO, CHARLOTTE, NC 28242 USA
来源
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1984年 / 46卷
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:50 / 52
页数:3
相关论文
共 50 条
  • [1] TRANSPORTABLE MODULAR VOLUME REDUCTION AND SOLIDIFICATION SYSTEM.
    Rodriguez, Luis F.
    Nuclear Plant Safety, 1985, 3 (04): : 34 - 36
  • [2] DEVELOPMENT OF A PORTABLE VOLUME REDUCTION AND SOLIDIFICATION SYSTEM
    DARRIN, JC
    YAMAGUCHI, T
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 33 (NOV): : 411 - 412
  • [3] TRANSPORTABLE COMMODITY IRRADIATOR DESIGN AND FABRICATION
    FERRELL, NJ
    RADIATION PHYSICS AND CHEMISTRY, 1988, 31 (4-6): : 549 - 554
  • [5] INERT-CARRIER RADWASTE VOLUME REDUCTION AND SOLIDIFICATION SYSTEM
    GREEN, TA
    SHEELINE, RD
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 32 (JUN): : 696 - 697
  • [6] THE APPLICATION OF ALARA CONCEPTS TO THE DESIGN OF RADWASTE VOLUME REDUCTION AND SOLIDIFICATION SYSTEMS
    BALCHAN, JA
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1984, 46 : 55 - 56
  • [7] Design, fabrication, and testing of a prototype microthermophotovoltaic system
    Yang, WM
    Chou, SK
    Shu, C
    Xue, H
    Li, ZW
    JOURNAL OF MICROELECTROMECHANICAL SYSTEMS, 2004, 13 (05) : 851 - 856
  • [8] Design, Fabrication and Testing of Smart Lighting System
    Xavier, Nikhil
    Kumar, Arun
    Panda, Sanjib Kumar
    PROCEEDINGS OF 2016 FUTURE TECHNOLOGIES CONFERENCE (FTC), 2016, : 763 - 768
  • [9] ALARA CONSIDERATIONS IN THE DESIGN OF A VOLUME REDUCTION SYSTEM
    DELISE, WE
    KROHN, FM
    HOWARD, DR
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1984, 46 : 54 - 55
  • [10] EVALUATION OF RADIATION SOURCE TERMS FOR THE COMPONENTS OF A RADWASTE VOLUME REDUCTION AND SOLIDIFICATION SYSTEM
    YEH, CS
    TUOHY, JM
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1983, 44 : 477 - 478