Measurement of pressure loss throughout a clogged steam generator tube support plate in two-phase flow

被引:0
|
作者
Electricité de France – R&D Division, Fluid Mechanics, Energy and Environment Department , 6, quai Watier, Chatou [1 ]
78401, France
机构
来源
Nucl Eng Des | 2020年
关键词
Two phase flow;
D O I
暂无
中图分类号
学科分类号
摘要
引用
收藏
相关论文
共 50 条
  • [41] Research method and two-phase flow stability of the steam generator of HTR-10
    Ju, HM
    Xu, YH
    Huang, ZY
    Yu, Y
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2001, 38 (09) : 739 - 744
  • [43] Pressure losses of two-phase flow in a variable-diameter tube
    Novozhilov V.N.
    Baranov D.A.
    Chemical and Petroleum Engineering, 2012, 47 (11-12) : 717 - 724
  • [44] PRELIMINARY ANALYSIS OF TWO-PHASE FLOW IN A STEAM GENERATOR USING CUPID-SG
    Kim, Hyungrae
    Kim, Soo Hyoung
    Lee, Seung-Jun
    Park, Ik Kyu
    Yoon, Han Young
    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 3, 2014,
  • [45] FEATURES OF HEAT TRANSFER STUDY OF TWO-PHASE FLOW IN FURNACE WALL TUBE FOR VARIABLE PRESSURE OPERATION SUPERCRITICAL ONCE-THROUGH STEAM GENERATOR.
    Hori, Masayoshi
    Matsumoto, Seiichi
    Nakada, Tetsuro
    IHI Engineering Review (English Edition), 1982, 15 (01): : 31 - 38
  • [46] Phenomenon, method, and application of the two-phase flow instability in a nuclear reactor steam generator
    Su Y.
    Li X.
    Wu X.
    Zhang Z.
    Qinghua Daxue Xuebao/Journal of Tsinghua University, 2023, 63 (08): : 1184 - 1203
  • [47] EVALUATION OF PULSE-ECHO ULTRASOUND FOR STEAM GENERATOR TUBE-TO-SUPPORT PLATE GAP MEASUREMENT.
    Furgason, E.S.
    Newhouse, V.L.
    Electric Power Research Institute (Report) EPRI NP, 1982,
  • [48] INDUCED-VIBRATION ANALYSIS PROBE FOR MEASUREMENT OF STEAM GENERATOR TUBE-TO-SUPPORT PLATE CLEARANCE.
    Anon
    Electric Power Research Institute (Report) EPRI NP, 1982,
  • [49] Flow-induced vibration of nuclear steam generator U-tubes in two-phase flow
    Chu, In-Cheol
    Chung, Heung June
    Lee, Seungtae
    NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (05) : 1508 - 1515
  • [50] Restrained Bending Effect by the Support Plate on the Steam Generator Tube with Circumferential Cracks
    Kim, Hyun-Su
    Jin, Tae-Eun
    Kim, Hong-Deok
    Chung, Han-Sub
    Chang, Yoon-Suk
    Kim, Young-Jin
    TRANSACTIONS OF THE KOREAN SOCIETY OF MECHANICAL ENGINEERS A, 2007, 31 (02) : 277 - 284