Review on the steam-liquid separation in the steam generator of nuclear power plants

被引:13
|
作者
Wang, Mengyao [1 ]
Bo, Wang [1 ,2 ]
Xin, Guo [1 ]
Zhang, Jiayi [1 ]
Chao, Zhiyang [1 ]
Yang, Wang [1 ]
Chuan, Lu [3 ]
Yang, Wu [3 ]
Tian, Ruifeng [1 ,2 ]
机构
[1] Harbin Engn Univ, Coll Nucl Sci & Technol, Harbin 150001, Peoples R China
[2] Harbin Engn Univ, Heilongjiang Prov Key Lab Nucl Power Syst & Equipm, Harbin 150001, Peoples R China
[3] Nucl Power Inst China, Sci & Technol Reactor Syst Design Technol Lab, Chengdu 610213, Peoples R China
关键词
Steam-liquid separation; Steam generator; Corrugated plate dryer; Liquid film; Liquid droplet; DISPERSED ANNULAR RIVULET; CORRUGATED PLATE WALL; MESH MIST ELIMINATORS; THIN-FILM FLOW; HEAT-TRANSFER; PRESSURE-DROP; NUMERICAL-ANALYSIS; PHASE-SEPARATION; FLUID-FLOW; WATER FILM;
D O I
10.1016/j.anucene.2022.109207
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
Steam-liquid desiccators (SLDs) as an important nuclear energy conversion equipment are widely used steam-liquid separation (SLS) devices of steam generator (SG) in advanced nuclear power systems (ANPS), which have been applied since the birth of the advanced pressurized-water reactor (APWR). SLDs are important energy conversion equipment in nuclear power plants (NPPs), and the steam-liquid separation efficiency (SLSE) of SLDs determines the energy conversion efficiency of NPPs. Thus there are a lot of heat and mass transfer phenomena in SLDs. The commonly used desiccators in steam generators are mainly corrugated plate desiccator (CPD), swirl-vane separator (SVS) and screen desiccator (SD). The current article presents an overview of the research status of the of steam-liquid separation mechanism (SLSM) and SLSE of desiccators in SG. The technical maturity and future application prospects of different SLDs were discussed in detail. Some discussions and suggestions on further research on desiccator are put forward. The literature review indicated that there is a certain degree of difficulty in the study on SLSM of desiccator. Thus, very few analyses and experiments on thermal-hydraulic performance such as the droplet movement and liquid film rupture mechanism (LFRM) in desiccator have been carried out. Most researches focus on experimental studies on the influence of structural parameters on SLSE of desiccator. Only by improving the SLSE of desiccators in ANPS can the nuclear energy conversation (conversation of nuclear energy to steam kinetic energy) efficiency be improved. (c) 2022 Elsevier Ltd. All rights reserved.
引用
收藏
页数:27
相关论文
共 50 条
  • [21] Transient analysis and dynamic modeling of the steam generator water level for nuclear power plants
    Sun, Xinyu
    Song, Fei
    Yuan, Jingqi
    PROGRESS IN NUCLEAR ENERGY, 2024, 170
  • [22] Development of Magnetic Phase Detection Sensor for the Steam Generator Tube in Nuclear Power Plants
    Son, Derac
    Joung, Won Ik
    Park, Duck-Gun
    Ryu, Kwon Sang
    JOURNAL OF MAGNETICS, 2009, 14 (02) : 97 - 100
  • [23] Evaluation of Heat Recovery Steam Generator for Gas/Steam Combined Cycle Power Plants
    Sharma, Achintya
    Sharma, Meeta
    Shukla, Anoop Kumar
    Negi, Nitin
    ADVANCES IN FLUID AND THERMAL ENGINEERING, 2019, : 189 - 200
  • [24] STEAM GENERATOR MODAL ANALYSIS OF NUCLEAR POWER PLANT
    Yan, Lu
    Chu Qibao
    Qing, Wang
    Fan Yonggang
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 2, 2017,
  • [25] STEAM GENERATOR REPAIR AT NUCLEAR POWER PLANT.
    Cookson, D.L.
    Stoof, Jack H.H.
    Dominguez, Jorge Jimenez
    Chartered Mechanical Engineer, 1981, 28 (02): : 27 - 32
  • [26] Level control in the steam generator of a nuclear power plant
    Kothare, MV
    Mettler, B
    Morari, M
    Bendotti, P
    Falinower, CM
    IEEE TRANSACTIONS ON CONTROL SYSTEMS TECHNOLOGY, 2000, 8 (01) : 55 - 69
  • [27] Level control in the steam generator of a nuclear power plant
    Kothare, MV
    Mettler, B
    Morari, M
    Bendotti, P
    Falinower, CM
    PROCEEDINGS OF THE 35TH IEEE CONFERENCE ON DECISION AND CONTROL, VOLS 1-4, 1996, : 4851 - 4856
  • [28] COMPUTATION OF THE STEAM-LIQUID EQUILIBRIUM OF TERNARY-SYSTEMS
    GOTTSCHLING, GS
    WOHNER, HJ
    TECHNISCHE MITTEILUNGEN KRUPP FORSCHUNGSBERICHTE, 1983, 41 (01): : 49 - 57
  • [29] Determination of steam wetness in the steam-generating equipment of nuclear power plants
    Gorburov V.I.
    Gorburov D.V.
    Kuz'min A.V.
    Thermal Engineering, 2012, 59 (05) : 390 - 394
  • [30] On an approach to diagnostics and monitoring of steam turbine installations of steam and nuclear power plants
    Dobrovol'skij, A.A.
    Sokolov, A.G.
    Problemy Mashinostraeniya i Nadezhnos'ti Mashin, 2002, (03): : 109 - 114