Numerical analysis of dryout and post-dryout heat transfer in once-through steam generator

被引：0

作者：

Shi J. ^{[1
]}

Sun B. ^{[1
]}

Zhao Y. ^{[1
]}

Liu S. ^{[1
]}

Zhang L. ^{[1
]}

机构：

[1] College of Power and Energy Engineering, Harbin Engineering University, Harbin, 150001, Heilongjiang

来源：

Huagong Xuebao/CIESC Journal | 2016年 / 67卷 / S1期

基金：

中国国家自然科学基金;

关键词：

Coupled method; Dryout; Heat flux partition; Heat transfer; Multiphase flow; Phase change;

D O I：

10.11949/j.issn.0438-1157.20160519

中图分类号：

学科分类号：

摘要：

It is significant to accurately predict the flow boiling and dryout for the design, safe and reliable operation of once-through steam generators. The once-through steam generator of B&W company is simplified reasonably, the two-fluid three-flow-field mathematical model and wall heat flux partition model are introduced to simulate the flow boiling in actual steam generator based on constant heat flux and coupled method respectively. The results show that: Heat transfer performance declines sharply when dryout occurs, soaring maximum of the wall temperature at constant heat flux is considerable (about 300 K·m-1), while a soaring maximum of 25 K·m-1 at coupled method, which is consistent with the actual operating process. The subcooled boiling occurs in preheating region at both thermal boundaries and the heat transfer methods near the wall consist of liquid convective, evaporation and quenching heat transfer. The main heat transfer method in nucleate boiling region is evaporation, accompanied with liquid convective and quenching heat transfer. The liquid convective and quenching heat transfer all drop to 0 when dryout occurs and the heat transfer method is vapor phase convective heat transfer in post-dryout heat transfer region. © All Right Reserved.

引用

页码：239 / 245

页数：6

共 20 条

[11]

Wang Z.L., Tian W.X., Su G.H., Et al., Development of a thermal hydraulic code for an integral reactor, Progress in Nuclear Energy, 68, pp. 31-42, (2013)

[12]

Zhao L., Guo L., Bai B., Et al., Convective boiling heat transfer and two-phase flow characteristics inside a small horizontal helically coiled tubing once-through steam generator, International Journal of Heat and Mass Transfer, 46, 25, pp. 4779-4788, (2003)

[13]

Jayanti S., Valette M., Prediction of dryout and post-dryout heat transfer at high pressures using a one-dimensional three-fluid model, International Journal of Heat and Mass Transfer, 47, 22, pp. 4895-4910, (2004)

[14]

Li H., Vasquez S.A., Punekar H., Et al., Prediction of boiling and critical heat flux using an eulerian multiphase boiling model, ASME 2011 International Mechanical Engineering Congress and Exposition, pp. 463-476, (2011)

[15]

Azzopardi B.J., Prediction of dryout and post-burnout heat transfer with axially non-uniform heat input by means of an annular flow model, Nuclear Engineering and Design, 163, 1, pp. 51-57, (1996)

[16]

Thurgood M.J., Kelly J.M., Guidotti T.E., Et al., COBRA/TRAC-a Thermal-Hydraulics Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems, pp. 21-38, (1983)

[17]

Weisman J., Pei B.S., Prediction of critical heat flux in flow boiling at low qualities, International Journal of Heat and Mass Transfer, 26, 10, pp. 1463-1477, (1983)

[18]

Sun B., Yang Y., Numerically investigating the influence of tube support plates on thermal-hydraulic characteristics in a steam generator, Applied Thermal Engineering, 51, 1, pp. 611-622, (2012)

[19]

Hoyer N., Calculation of dryout and post-dryout heat transfer for tube geometry, International Journal of Multiphase Flow, 24, 2, pp. 319-334, (1998)

[20]

Babcock & Wilcox Company, Pressurized water reactor B&W technology crosstraining course manual, (2011)

← 1 2 →