Effect of Pressure on Steady State and Heat Transfer Characteristics in Supercritical CO2 Natural Circulation Loop

被引:14
作者
Archana, V [1 ]
Vaidya, A. M. [2 ]
Vijayan, P. K. [2 ]
机构
[1] Homi Bhabha Natl Inst, Bombay 400094, Maharashtra, India
[2] Bhabha Atom Res Ctr, Bombay 400085, Maharashtra, India
来源
INTERNATIONAL CONFERENCE ON COMPUTATIONAL HEAT AND MASS TRANSFER (ICCHMT) - 2015 | 2015年 / 127卷
关键词
Supercritical CO2; Natural circulation loop; Heat transfer; Supercritical water reactor; Vertical heater vertical cooler;
D O I
10.1016/j.proeng.2015.11.355
中图分类号
O414.1 [热力学];
学科分类号
摘要
A 2D axi-symmetric CFD code (NAFA-LOOP) has been developed for studying the heat transfer and steady state characteristics of supercritical CO2 natural circulation loop (SPNCL). NAFA-Loop is derived from the pipe flow solver (NAFA) which was developed earlier to study the heat transfer characteristics of supercritical fluid pipe flow. The code is validated at supercritical condition with experimental results. Effect of pressure on heat transfer and steady state characteristics has been studied by keeping all the operating parameters such as secondary side coolant flow rate and secondary side coolant inlet temperature constant except the pressure. And the heater power is varied from 200 W to 3000 W for each pressure. As increasing the pressure, the steady state mass flow rate increases because of increase in the density difference in loop (driving force). But the maximum value of heat transfer coefficient decreases as increasing the pressure. (C) 2015 The Authors. Published by Elsevier Ltd.
引用
收藏
页码:636 / 644
页数:9
相关论文
共 8 条
[1]   The stability boundary for supercritical flow in natural convection loops Part I:: H2O studies [J].
Chatoorgoon, V ;
Voodi, A ;
Fraser, D .
NUCLEAR ENGINEERING AND DESIGN, 2005, 235 (24) :2570-2580
[2]   Discussion on the stability of natural circulation loops with supercritical pressure fluids [J].
Debrah, Seth Kofi ;
Ambrosini, Walter ;
Chen, Yuzhou .
ANNALS OF NUCLEAR ENERGY, 2013, 54 :47-57
[3]  
Patankar SV., 2009, Numerical heat transfer and fluid flow, V1
[4]  
Sharma M., 2010, J ENG GAS TURB POWER, V132
[5]  
Sharma M., 2013, BARC2013E002
[6]   FEASIBILITY OF COOLING HEAVY-WATER REACTORS WITH SUPERCRITICAL FLUIDS [J].
TOM, SKS ;
HAUPTMANN, EG .
NUCLEAR ENGINEERING AND DESIGN, 1979, 53 (02) :187-196
[7]  
Vaidya A. M., 2010, BARC2010E001
[8]  
Vijayan P. K., 2013, BARC2013E003