Theoretical analysis about model simplifications and boundary conditions on two-phase flow instability of parallel heated tube systems

被引:2
作者
Su, Yang [1 ]
Li, Xiaowei [1 ]
Fan, Hongyi [1 ]
Wu, Xinxin [1 ]
机构
[1] Tsinghua Univ, Inst Nucl & New Energy Technol, Collaborat Innovat Ctr Adv Nucl Energy Technol, Key Lab Adv Reactor Engn & Safety,Minist Educ, Beijing 100084, Peoples R China
基金
中国国家自然科学基金;
关键词
Two-phase flow instability; Linear ordinary differential equations; Similarity matrix; Boundary conditions; Multiple parallel heated tubes; Dimensionless pump number; Dimensionless bypass number; DENSITY WAVE INSTABILITIES; REDUCED-ORDER MODEL; STABILITY ANALYSIS; STEAM-GENERATOR; SUPERCRITICAL PRESSURE; DYNAMIC INSTABILITIES; LEDINEGG INSTABILITY; NATURAL CIRCULATION; FRICTION FACTOR; HELICAL TUBE;
D O I
10.1016/j.nucengdes.2023.112700
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
Flow instability may happen in both subcritical two-phase flow boiling systems (such as U tube natural circulation steam generator of Pressurized Water Reactor, once through steam generator of High-Temperature GasCooled Reactor, etc) and supercritical evaporation systems. In previous theoretical researches, the model of a single heated tube (SHT) with constant pressure drop boundary condition (ConPD) was always used to investigate the system stability. However, in real applications, there are usually multiple parallel heated tubes (MHT) and unheated connection regions before the branch heated tubes. The system is usually driven by a pump, and there is always a long unheated main pipe and throttling between the heated tubes (boiler or steam generator) and the pump. However, there lacks rigorous analysis about the effects of these model simplifications and boundary conditions. Take superheated two-phase flow boiling systems as examples, the theoretical models with different flow-driven boundary conditions (ConPD, constant mass flow rate (ConMF), and pump driven (PumpD)), different numbers of heat tubes (SHT, MHT), with or ignoring the unheated region (UHR), with or ignoring the bypass of a pump, with identical or un-identical geometry parameters and operation parameters are established. Linear ordinary differential equations describing the instability are obtained. Eigenvalues of the coefficient matrix of linear ordinary differential equations, and the property of the block matrix and the similarity matrix are used to analyze the effects of the above boundary conditions and model simplifications on the system stability. Two new dimensionless numbers, dimensionless pump number (Npump) and dimensionless bypass number (Nbypass), are proposed to describe the effect of pump and its bypass on stability quantitatively. The effect of the pump bypass on the stability can be attributed to the decrease of Npump. No matter ConPD or PumpD is adopted, SHT considering UHR is proved to be more stable than SHT ignoring UHR. No matter UHR is considered or ignored, SHT with PumpD is proved to be more stable than SHT with ConPD. No matter UHR of MHT at the main pipe is considered or ignored, the stability of MHT with ConPD or ConMF or PumpD is proved to be the same as that of SHT with ConPD ignoring UHR. When ConPD ignoring UHR is adopted, the stability of MHT with un-identical geometry and operation parameters is proved to be the same as that of its most unstable heated tube. The above conclusions about the effect of model simplification and boundary condition are obtained from superheated two-phase flow boiling systems, they also hold for saturated two-phase flow boiling systems and supercritical evaporation systems.
引用
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页数:20
相关论文
共 70 条
[1]   THE EFFECT OF GRAVITY AND FRICTION ON THE STABILITY OF BOILING FLOW IN A CHANNEL [J].
Achard, J. L. ;
Drew, D. A. ;
Lahey, R. T., Jr. .
CHEMICAL ENGINEERING COMMUNICATIONS, 1981, 11 (1-3) :59-79
[2]  
Akagawa Koji., 1971, Bulletin of JSME, V14, P837
[3]   Dimensionless parameters in stability analysis of heated channels with fluids at supercritical pressures [J].
Ambrosini, Walter ;
Sharabi, Medhat .
NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (08) :1917-1929
[4]   Discussion on the stability of heated channels with different fluids at supercritical pressures [J].
Ambrosini, Walter .
NUCLEAR ENGINEERING AND DESIGN, 2009, 239 (12) :2952-2963
[5]  
Bai Y.F., 2019, MS thesis
[6]  
[白宇飞 Bai Yufei], 2020, [哈尔滨工业大学学报, Journal of Harbin Institute of Technology], V52, P28
[7]   CONSTRUCTION AND OPERATING EXPERIENCE WITH THE 300-MW THTR NUCLEAR-POWER-PLANT [J].
BAUMER, R ;
KALINOWSKI, I ;
ROHLER, E ;
SCHONING, J ;
WACHHOLZ, W .
NUCLEAR ENGINEERING AND DESIGN, 1990, 121 (02) :155-166
[8]  
BOURE JA, 1973, NUCL ENG DES, V25, P165, DOI 10.1016/0029-5493(73)90043-5
[9]   Two-phase flow instabilities: A review [J].
Carlos Ruspini, Leonardo ;
Pablo Marcel, Christian ;
Clausse, Alejandro .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2014, 71 :521-548
[10]   Near-Critical Natural Circulation Flows Inside an Experimental Loop: Stability Map and Heat Transfer [J].
Chen, Lin ;
Zhang, Xin-Rong ;
Deng, Bi-Li .
HEAT TRANSFER ENGINEERING, 2016, 37 (3-4) :302-313