SLEEVING SAVES NUCLEAR STEAM GENERATOR TUBES.

被引:0
|
作者
Olds, F.C.
机构
来源
Geotechnical Engineering | 1981年 / 85卷 / 12期
关键词
Compendex;
D O I
暂无
中图分类号
学科分类号
摘要
NUCLEAR POWER PLANTS
引用
收藏
页码:73 / 75
相关论文
共 50 条
  • [21] Development of wear test system for steam generator tubes in nuclear power plants
    Park, CY
    Lee, YS
    Boo, MH
    ADVANCES IN FRACTURE AND STRENGTH, PTS 1- 4, 2005, 297-300 : 1418 - 1423
  • [22] COUNTERACTING MULTIPATH EFFECTS IN GAP MEASUREMENT OF NUCLEAR STEAM-GENERATOR TUBES
    AMIR, I
    NEWHOUSE, VL
    FURGASON, ES
    IEEE TRANSACTIONS ON SONICS AND ULTRASONICS, 1982, 29 (03): : 189 - 189
  • [23] Development of an integrity evaluation system for steam generator tubes in a nuclear power plant
    Kim, J. C.
    Lee, S. M.
    Chang, Y. S.
    Choi, J. B.
    Kim, Y. J.
    Choi, Y. H.
    SAFETY AND STRUCTURAL INTEGRITY 2006, 2007, 120 : 157 - +
  • [24] Evaluation of fretting fatigue life for steam generator tubes in nuclear power plants
    Park, Dae-Kyu
    Woo, Seung-Wan
    Chung, II-Sub
    Chai, Young-Suck
    Kwon, Jae-Do
    MECHANICAL BEHAVIOR OF MATERIALS X, PTS 1AND 2, 2007, 345-346 : 243 - +
  • [25] Fluidelastic instability analysis of operating nuclear steam generator U-tubes
    Jo, JC
    Shin, WK
    NUCLEAR ENGINEERING AND DESIGN, 1999, 193 (1-2) : 55 - 71
  • [26] Experimental determination of J-resistance curves of nuclear steam generator tubes
    Bergant, Marcos A.
    Yawny, Alejandro A.
    Perez Ipina, Juan E.
    ENGINEERING FRACTURE MECHANICS, 2016, 164 : 1 - 18
  • [27] CRITICAL STEAM (GAS) VELOCITY FOR THE PROCESS OF FLOODING IN VERTICAL TUBES.
    Sorokin, Yu.L.
    Sorokin, M.Yu.
    Soviet Energy Technology (English translation of Energomashinostroenie), 1985, (06): : 9 - 16
  • [28] HEAT TRANSFER ENHANCEMENT IN FINNED STEAM-GENERATING TUBES.
    Minchenko, F.P.
    Shvartsman, G.S.
    Heat transfer. Soviet research, 1979, 11 (02): : 14 - 23
  • [29] EXPERIENCE WITH STEAM-GENERATOR TUBES IN WATER-COOLED NUCLEAR OPTIONAL PLANTS
    TATONE, OS
    PATHANIA, RS
    NUCLEAR ENGINEERING INTERNATIONAL, 1978, 23 (269): : 35 - 39
  • [30] EXPERIENCE WITH STEAM-GENERATOR TUBES IN WATER-COOLED NUCLEAR OPTIONAL PLANTS
    TATONE, OS
    PATHANIA, RS
    NUCLEAR ENGINEERING INTERNATIONAL, 1978, 23 (270): : 35 - 39