Mechanistic modelling of dryout and post-dryout heat transfer

被引：8

作者：

Anglart, Henryk ^{[1
]}

Li, Haipeng ^{[1
]}

Niewinski, Grzegorz ^{[2
]}

机构：

[1] KTH Royal Inst Technol, Sch Engn Sci, Dept Phys, Roslagstullsbacken 21, S-10691 Stockholm, Sweden

[2] Warsaw Univ Technol, Inst Heat Engn, Nowowiejska 21-25, PL-00665 Warsaw, Poland

来源：

ENERGY | 2018年 / 161卷

关键词：

Dryout; Post-dryout; Annular flow; Liquid film; Droplets; ANNULAR 2-PHASE FLOW; FILM FLOW; DROP DEPOSITION; PREDICTION; LIQUID;

D O I：

10.1016/j.energy.2018.07.011

中图分类号：

O414.1 [热力学];

学科分类号：

摘要：

In this paper a new mechanistic model for the diabatic annular two-phase flow is presented and applied to prediction of dryout and post-dryout heat transfer in various channels. The model employs a computational fluid dynamics code - OpenFOAM (R) - to solve the governing equations of two-phase mixture flowing in a heated channel. Additional closure laws have been implemented to calculate the location of the dryout and to predict wall temperature in the post-dryout region. Calculated results have been compared with experimental data obtained in pipes and good agreement between predictions and measurements has been achieved. The presented model is applicable to complex geometries and thus can be used for prediction of post-dryout heat transfer in a wide variety of energy conversion systems. (C) 2018 Elsevier Ltd. All rights reserved.

引用

页码：352 / 360

页数：9

共 43 条

[1]

Adamsson C., 2006, P INT WORKSH MOD MEA

[2]

Adamsson C., 2007, P 12 INT TOP M NUCL

[3]

Adamsson C., 2004, P 6 INT C NUCL THERM

[4] Film flow measurements for high-pressure diabatic annular flow in tubes with various axial power distributions [J].

Adamsson, Carl ;

Anglart, Henryk .

NUCLEAR ENGINEERING AND DESIGN, 2006, 236 (23) :2485-2493

[5] Influence of axial power distribution on dryout: Film-flow models and experiments [J].

Adamsson, Carl ;

Anglart, Henryk .

NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (06) :1495-1505

[6]

Anglart H., 1997, Eighth International Topical Meeting on Nuclear Reactor Thermal-Hydraulics. NURETH-8. New Horizons in Nuclear Reactor Thermal-Hydraulics, P1647

[7]

Anglart H., 2003, P 10 INT TOP M NUCL

[8]

Anglart H., 1994, P 2 CFDS INT US C PI

[9]

Anglart H., 2015, P INT SEM SUBCH AN I

[10]

Anglart H., 2002, EUR 2 PHAS FLOW GROU

← 1 2 3 4 5 →