Nanofluid application in post SB-LOCA transient in VVER-1000 NPP

被引:9
|
作者
Hadad, Kamal [1 ]
Rahimian, Aref [1 ]
Rabiee, Ataollah [1 ]
机构
[1] Shiraz Univ, Sch Mech Engn, Shiraz, Iran
关键词
Nanofluid; SB-LOCA; VVER-1000; CFD; Flow boiling; HEAT-TRANSFER; FLOW; CONVECTION; MODEL;
D O I
10.1016/j.anucene.2015.01.024
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
This paper is the third in a series of four papers that the application of nanofluid as a coolant to improve heat transfer in a VVER-1000 nuclear reactor is investigated. In the first and second papers, neutronics and thermo-hydraulic behavior of nano-particles in normal operation mode of the reactor were reported. In this study, the effects of nanofluids in Small Break Loss of Coolant Accident (SB-LOCA) to complement the existing safety systems is investigated. During SB-LOCA transient, due to reduced mass flow rate and Reynolds number, flow boiling along with vapor formation around the fuel rods occur. The fuel assembly coolant channel of a VVER-1000 core is modeled using a CFD code and heat transfer coefficients, pressure drop and volume fraction distribution of phases are computed for water/Al2O3 nanofluid. We observe that with the escalation of heat transfer enhancement, due to reduction in void fraction, pressure drop along the channel is reduced. This new phenomenon of lower pressure drop along with heat transfer enhancement, would be a significant factor for the use of nanofluids during reactor SB-LOCA transients. (C) 2015 Elsevier Ltd. All rights reserved.
引用
收藏
页码:101 / 110
页数:10
相关论文
共 50 条
  • [41] Investigation of xenon transient processes in VVER-1000 at the Tianwan nuclear power plant (China)
    S. P. Aver’yanova
    K. B. Kosourov
    Yu. M. Semchenkov
    P. E. Filimonov
    Liu Haitao
    Li Youyi
    [J]. Atomic Energy, 2008, 105 : 231 - 241
  • [42] Numerical simulation of turbulent natural convection of oxide heat generating melt in a core catcher at NPP with VVER-1000
    A. S. Filippov
    [J]. Journal of Engineering Thermophysics, 2011, 20
  • [43] Numerical Simulation of Turbulent Natural Convection of Oxide Heat Generating Melt in a Core Catcher at NPP with VVER-1000
    Filippov, A. S.
    [J]. JOURNAL OF ENGINEERING THERMOPHYSICS, 2011, 20 (02) : 161 - 173
  • [44] Investigation of small break LOCA with failure of the emergency core cooling system accident management in VVER-1000 reactor type
    Vahman, Navid
    Ghasemi, Maryam
    Amrollahi, Reza
    Sohrabi, Mehdi
    [J]. ANNALS OF NUCLEAR ENERGY, 2023, 183
  • [45] Study of in-containment source term behavior for VVER-1000 under LOCA conditions using the IRBURN code system
    Jafarikia, S.
    Feghhi, S. A. H.
    [J]. ANNALS OF NUCLEAR ENERGY, 2018, 112 : 17 - 29
  • [46] RETRACTED: Subchannel analysis of TiO2 nanofluid as the coolant in VVER-1000 reactor (Retracted Article)
    Zarifi, Ehsan
    Jahanfarnia, Gholamreza
    [J]. PROGRESS IN NUCLEAR ENERGY, 2014, 73 : 140 - 152
  • [47] Study of Fast Transient Pressure Drop in VVER-1000 Nuclear Reactor Using Acoustic Phenomenon
    Sangestani, Soroush Heidari
    Rahgoshay, Mohammad
    Vosoughi, Naser
    Allaf, Mitra Athari
    [J]. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2018, 2018
  • [48] Validation of the Serpent 2-HEXTRAN-SMABRE code sequence in a VVER-1000 coolant transient
    Hakkinen, Silja
    Syrjalahti, Elina
    Rintala, Antti
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2020, 57 (10) : 1167 - 1180
  • [49] Reloading pattern optimization of VVER-1000 reactors (in transient cycles) using imperialist competitive algorithm
    Rahmani, Yashar
    Shahvari, Yaser
    Kia, Faezeh
    [J]. PROGRESS IN NUCLEAR ENERGY, 2016, 93 : 327 - 342
  • [50] Improving the transient stability of VVER-1000 reactor-based nuclear power plant units
    Kazakov V.A.
    Zhudenkov V.V.
    Kazakov K.V.
    Povarov V.P.
    Vitkovskii I.L.
    [J]. Thermal Engineering, 1600, Izdatel'stvo Nauka (61): : 47 - 53