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
  • [1] Re-assessment of accumulators performance to identify VVER-1000 vulnerabilities against various break sizes of SB-LOCA along with SBO
    Hosseini, Seyed Ali
    Shirani, Amir Saeed
    Zangian, Mandi
    Najafi, Alireza
    [J]. PROGRESS IN NUCLEAR ENERGY, 2020, 119
  • [2] BEST ESTIMATE SIMULATION AND UNCERTAINTY ANALYSIS OF LB LOCA FOR KUDANKULAM VVER-1000 NPP
    Sabotinov, Luben
    Srivastava, Abhishek
    Probst, Pierre
    [J]. PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 2, 2009, : 765 - 775
  • [3] SAFETY ANALYSIS ON MITIGATION OVERPRESSURE ATWS IN VVER-1000 NPP
    Qi Ting
    Yang Changjiang
    [J]. PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 3, 2014,
  • [4] The seismic reliability of VVER-1000 NPP prestressed containment building
    Varpasuo, P
    [J]. NUCLEAR ENGINEERING AND DESIGN, 1996, 160 (03) : 387 - 398
  • [5] DYNAMIC MODEL OF THE VVER-1000 REACTOR FOR SEISMIC AND LB LOCA EVALUATION
    Ishchenko, Oleksii
    Filonov, Vladislav
    Dubyk, Yaroslav
    [J]. PROCEEDINGS OF 2021 28TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE28), VOL 4, 2021,
  • [6] STUDY ON IMPACTS OF ADS ON AP1000 DURING SB-LOCA
    Chen, Long
    Lv, Xuefeng
    Wang, Shengfei
    Yu, Yu
    [J]. PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 6, 2014,
  • [7] Application of coulped code method for the analysis of VVER-1000 coolant transient benchmark
    Salah, Anis Bousbia
    D'Auria, Francesco
    [J]. PROGRESS IN NUCLEAR ENERGY, 2009, 51 (01) : 146 - 154
  • [8] Neutronic study of nanofluids application to VVER-1000
    Hadad, K.
    Hajizadeh, A.
    Jafarpour, K.
    Ganapol, B. D.
    [J]. ANNALS OF NUCLEAR ENERGY, 2010, 37 (11) : 1447 - 1455
  • [9] UNCERTAINTY ANALYSIS OF SB-LOCA IN AP1000 NUCLEAR POWER PLANT
    Shi, Hao
    Cai, Qi
    Chen, Yuqing
    Jiang, Lizhi
    [J]. PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 6, 2017,
  • [10] Load Effects Inside NPP VVER-1000 Containment Wall Cross Section
    V. N. Medvedev
    M. I. Skorikova
    Aleksandr S. Kiselev
    Aleksei S. Kiselev
    V. F. Strizhov
    A. N. Ul’yanov
    [J]. Atomic Energy, 2021, 130 : 20 - 24