Numerical investigations of thermal mixing performance of a hot gas mixing structure in high-temperature gas-cooled reactor

被引:7
作者
Zhou, Yang-Ping [1 ]
Hao, Peng-Fei [2 ]
Zhang, Xi-Wen [2 ]
He, Feng [2 ]
机构
[1] Tsinghua Univ, Inst Nucl & New Energy Technol, Key Lab Adv Reactor Engn & Safety, Minist Educ, Beijing 100084, Peoples R China
[2] Tsinghua Univ, Sch Aerosp, Beijing 100084, Peoples R China
基金
中国国家自然科学基金;
关键词
High-temperature gas-cooled reactor; Numerical simulation; Thermal mixing; Swirling flow; ENGINEERING TEST REACTOR; CORE BOTTOM STRUCTURE; SIMULATION; COOLANT; FLOW;
D O I
10.1007/s41365-016-0024-7
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
A numerical simulation study was performed to clarify the thermal mixing characteristics of coolant in the core bottom structure of the high-temperature gas-cooled reactor (HTR). The flow field and temperature field in the hot gas chamber and the hot gas duct of the HTR were obtained based on the commercial computational fluid dynamics (CFD) program. The numerical simulation results showed that the helium flow with different temperatures in the hot gas mixing chamber and the hot gas duct mixed intensively, and the mixing rate of the temperature in the outlet of the hot gas duct reached 98 %. The results indicated many large-scale swirling flow structures and strong turbulence in the hot gas mixing chamber and the entrance of the hot gas duct, which were responsible for the excellent thermal mixing of the hot gas chamber and the hot gas duct. The calculated results showed that the temperature mixing rate of the hot gas chamber decreased only marginally with increasing Reynolds number.
引用
收藏
页数:7
相关论文
共 12 条
[1]   SIMULATION TESTS FOR TEMPERATURE MIXING IN A CORE BOTTOM MODEL OF THE HTR-MODULE [J].
DAMM, G ;
WEHRLEIN, R .
NUCLEAR ENGINEERING AND DESIGN, 1992, 137 (01) :97-105
[2]  
Hishida M., 1987, P HEM PUBL CO, P273
[3]   THERMAL MIXING TEST OF COOLANT IN THE CORE BOTTOM STRUCTURE OF A HIGH-TEMPERATURE ENGINEERING TEST REACTOR [J].
INAGAKI, Y ;
KUNUGI, T ;
MIYAMOTO, Y .
NUCLEAR ENGINEERING AND DESIGN, 1990, 123 (01) :77-86
[4]   THERMAL-HYDRAULIC CHARACTERISTICS OF COOLANT IN THE CORE BOTTOM STRUCTURE OF THE HIGH-TEMPERATURE ENGINEERING TEST REACTOR [J].
INAGAKI, Y ;
KUNITOMI, K ;
MIYAMOTO, Y ;
IOKA, I ;
SUZUKI, K .
NUCLEAR TECHNOLOGY, 1992, 99 (01) :90-103
[5]   CFD evaluation of turbulence models for flow simulation of the fuel rod bundle with a spacer assembly [J].
Liu, C. C. ;
Ferng, Y. M. ;
Shih, C. K. .
APPLIED THERMAL ENGINEERING, 2012, 40 :389-396
[6]  
Luo Xiang, 2012, Journal of Aerospace Power, V27, P2188
[7]   Experimental and CFD investigation on mixing by a jet in a semi-industrial stirred tank [J].
Rahimi, M ;
Parvareh, A .
CHEMICAL ENGINEERING JOURNAL, 2005, 115 (1-2) :85-92
[8]  
Song S.X., 2013, NUCL TECH, V36
[9]   Thermal-hydraulics analyses for 1/6 prismatic VHTR core and fuel element with and without bypass flow [J].
Travis, Boyce W. ;
El-Genk, Mohamed S. .
ENERGY CONVERSION AND MANAGEMENT, 2013, 67 :325-341
[10]   Simulating test for thermal mixing in the hot gas chamber of the HTR-10 [J].
Yao, MS ;
Huang, ZY ;
Ma, CW ;
Xu, YH .
NUCLEAR ENGINEERING AND DESIGN, 2002, 218 (1-3) :233-240