INSPECTING STEAM-GENERATOR TUBES WITH A ROTATING UT SYSTEM

被引:0
|
作者
GLASS, SW
SHACKELFORD, SW
机构
来源
NUCLEAR ENGINEERING INTERNATIONAL | 1989年 / 34卷 / 417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:41 / 42
页数:2
相关论文
共 50 条
  • [21] LEAK-BEFORE-BREAK IN STEAM-GENERATOR TUBES
    FLESCH, B
    COCHET, B
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1990, 43 (1-3) : 165 - 179
  • [22] A STEAM-GENERATOR INTEGRITY SURVEILLANCE SYSTEM
    BANOVEC, J
    MATAL, O
    KONARIK, M
    VYTOPIL, O
    PRIDOHL, E
    FROHLICH, KJ
    MAUERSBERGER, H
    KERNENERGIE, 1984, 27 (03): : 105 - 107
  • [23] STEAM-GENERATOR SYSTEM FOR CLINCH RIVER
    SKAVDAHL, RE
    TIPPETS, FE
    NUCLEAR ENGINEERING INTERNATIONAL, 1974, 19 (221): : 857 - 860
  • [24] STEAM-GENERATOR NOZZLE DAM SYSTEM
    ZEZZA, LJ
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1985, 50 (NOV): : 412 - 413
  • [25] STRESS IDENTIFICATION IN STEAM-GENERATOR TUBES FROM PROFILE MEASUREMENTS
    ANDRIEUX, S
    VOLDOIRE, F
    NUCLEAR ENGINEERING AND DESIGN, 1995, 158 (2-3) : 417 - 427
  • [26] FAILURE ANALYSIS OF STEAM-GENERATOR TUBES WITH DENTED AND WASTAGE CONFIGURATIONS
    REICH, M
    PRACHUKTAM, S
    CHANG, TY
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 1978, 100 (04): : 354 - 359
  • [27] RELIABILITY OF EDDY-CURRENT EXAMINATION OF STEAM-GENERATOR TUBES
    BIRKS, AS
    MATERIALS EVALUATION, 1985, 43 (10) : 1303 - 1303
  • [28] FLOW-INDUCED VIBRATION AND WEAR OF STEAM-GENERATOR TUBES
    CONNORS, HJ
    NUCLEAR TECHNOLOGY, 1981, 55 (02) : 311 - 331
  • [29] SODIUM FLOW-INDUCED VIBRATION IN STEAM-GENERATOR TUBES
    SMITH, JO
    MCCARTHY, JH
    BOELTER, WA
    BRENNAN, JH
    MECHANICAL ENGINEERING, 1965, 87 (07) : 71 - &
  • [30] PROPAGATION OF STRESS-CORROSION CRACKS IN STEAM-GENERATOR TUBES
    CIZELJ, L
    MAVKO, B
    RIESCHOPPERMANN, H
    BRUCKERFOIT, A
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1995, 63 (01) : 35 - 43