Steam generator tube flow rate regulation of HTGR steam generator test loop

被引:0
|
作者
Li, Xiao-Wei [1 ]
Wu, Xin-Xin [1 ]
Ju, Huai-Ming [1 ]
机构
[1] Reactor Structure Division, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China
来源
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2012年 / 46卷 / SUPPL.2期
关键词
Atmosphere pressure - HTGR - Rate variation - Steam generator tube - Step size - Two-valves;
D O I
暂无
中图分类号
学科分类号
摘要
引用
收藏
页码:859 / 862
相关论文
共 50 条
  • [21] Studies on flow instability of helical tube steam generator with Nyquist criterion
    Niu, Fenglei
    Tian, Li
    Yu, Yu
    Li, Rizhu
    Norman, Timothy L.
    NUCLEAR ENGINEERING AND DESIGN, 2014, 266 : 63 - 69
  • [22] FACTORS AFFECTING STEAM GENERATOR TUBE BOW
    Cao, Moli
    Nelson, Jennifer
    Charkas, Hasan
    Wiger, Timothy
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2013, VOL 3: DESIGN AND ANALYSIS, 2014,
  • [23] FLOW DISTRIBUTION AT THE BOTTOM REGION OF A STEAM-GENERATOR TUBE BUNDLE
    PADMANABHAN, M
    LECLAIR, ML
    CHANDRA, S
    GRONDAHL, E
    NUCLEAR ENGINEERING AND DESIGN, 1992, 133 (01) : 169 - 180
  • [24] Steam generator tube rupture (SGTR) scenarios
    Auvinen, A
    Jokiniemi, JK
    Lähde, A
    Routamo, T
    Lundström, P
    Tuomisto, H
    Dienstbier, J
    Güntay, S
    Suckow, D
    Dehbi, A
    Slootman, M
    Herranz, L
    Peyres, V
    Polo, J
    NUCLEAR ENGINEERING AND DESIGN, 2005, 235 (2-4) : 457 - 472
  • [25] STEAM-GENERATOR TUBE DENT CHARACTERIZATION
    RICHARDS, T
    MATERIALS EVALUATION, 1982, 40 (10) : 27 - 27
  • [26] STEAM-GENERATOR TUBE REPAIR BY SLEEVING
    HORLACHER, WR
    HAAS, KM
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 28 (JUN): : 601 - 603
  • [27] STEAM-GENERATOR TUBE VIBRATION TESTS
    ENDERLIN, WI
    NUCLEAR ENGINEERING AND DESIGN, 1985, 89 (2-3) : 333 - 337
  • [28] EXPERIMENTAL INVESTIGATION OF SUBCOOLED CHOKING FLOW IN A STEAM GENERATOR TUBE CRACK
    Hung Nguyen
    Brown, Mark
    Revankar, Shripad T.
    Riznic, Jovica
    PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 5, 2016,
  • [29] REMEDY FOR STEAM-GENERATOR TUBE FAILURES
    REISCH, F
    NUCLEAR SAFETY, 1983, 24 (05): : 705 - 707
  • [30] Steam generator tube integrity - USNRC perspective
    Sullivan, EJ
    Murphy, EL
    NDE IN THE NUCLEAR AND PRESSURE VESSEL INDUSTRIES, 1997, : 135 - 140