Comparison Between Experimental Data and Numerical Modeling for the Natural Circulation Phenomenon

被引:10
作者
Sabundjian, Gaiane [1 ]
de Andrade, Delvonei A. [1 ]
Umbehaun, Pedro E. [1 ]
Torres, Walmir M. [1 ]
Macedo, Luiz A. [1 ]
Conti, Thadeu N. [1 ]
de Mesquita, Roberto N. [1 ]
Angelo, Gabriel [1 ]
机构
[1] Ctr Engn Nucl, IPEN CNEN SP, Inst Pesquisas Energet & Nucl, BR-05508000 Sao Paulo, Brazil
关键词
Natural Circulation; RELAP5; two-phase flow;
D O I
10.1590/S1678-58782011000500003
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
The study of natural circulation phenomenon has been object of crescent interest in scientific community in recent years. The new generation of compact nuclear reactors uses natural circulation of the fluid as a residual heat removal cooling system in case of accident or shutdown. The objective of this paper is to present a comparison between experimental data and numerical simulation results for the natural circulation phenomenon in single and two-phase flow regime. Experimental data were obtained from a circuit built with glass tubes, through which thermal hydraulic phenomenon visualization was possible. The circuit is composed of an electric heater as the heat source, a heat exchanger as the heat sink and an expansion tank to accommodate fluid density changes. Instrumentation data acquisition is performed through thermocouples and pressure meters, and controlled by a computer interface developed using LABVIEW. Numerical modeling and simulations were done with the thermal hydraulic code RELAP5, which is widely used for this purpose. The cyclic reverse flow observed in the circuit was well represented by the numerical model. The comparison demonstrated that the numerical simulations are very close to the experimental data.
引用
收藏
页码:227 / 232
页数:6
相关论文
共 12 条
[1]  
[Anonymous], 1999, NUREGCR5535 SCIENTEC
[2]  
[Anonymous], 1997, TEM ESP TERM 11 ENFI
[3]  
[Anonymous], 2003, LABVIEW 7 0 EXPR
[4]   NUR research reactor safety analysis study for long time natural convection (NC) operation mode [J].
Azzoune, M. ;
Mammou, L. ;
Boulheouchat, M. H. ;
Zidi, T. ;
Mokeddem, M. Y. ;
Belaid, S. ;
Salah, A. Bousbia ;
Meftah, B. ;
Boumedien, A. .
NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (04) :823-831
[5]  
Borges E.M, 2006, FAMILIARIZACAO PROGR
[6]  
BRAATEN ME, 1987, NUMER HEAT TRANSFER, V11, P417, DOI 10.1080/10407788708913563
[7]  
Jaluria Y., 1986, Computational Heat Transfer
[8]   Analysis of decay heat removal from RBMK-1500 reactor in decommissioning phase by natural circulation of water and air [J].
Kaliatka, Algirdas ;
Uspuras, Eugenijus ;
Vaisnoras, Mindaugas ;
Krivoshein, Georgij .
NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (05) :1242-1250
[9]   Thermal hydraulic analysis of Syrian MNSR research reactor using RELAP5/Mod3.2 code [J].
Omar, H. ;
Ghazi, N. ;
Alhabit, F. ;
Hainoun, A. .
ANNALS OF NUCLEAR ENERGY, 2010, 37 (04) :572-581
[10]  
Rocha R.T.V., 2008, EBECEM2008 FLOR