全部 标题 作者
关键词 摘要

OALib Journal期刊
ISSN: 2333-9721
费用:99美元

查看量下载量

相关文章

更多...
化工学报  2014 

基于查询表的环状流初始携带份额分析计算

, PP. 0-0

Keywords: 气液两相流,传质,传热,公式化,环状流,初始携带份额

Full-Text   Cite this paper   Add to My Lib

Abstract:

气液两相流临界热流密度对工业设备的安全性有重要影响,液膜干涸模型是预测气液相环状流临界热流密度的有效方法。确定环状流起始点、初始和平衡状态的携带份额、携带现象的发生条件、液滴沉积率以及携带率对模型的计算精度都起着决定性的作用。通过大量研究目前已经得到了适用于不同条件下的经验关联式来预测此模型中的大多数参数,然而环状流起始点的初始携带份额至今仍需通过假设来确定。以广泛应用于核工业的临界热流密度查询表为依据,针对界限含气率区间建立环状流液膜干涸模型,对使模型计算值满足查询表工况的初始携带份额进行分析,拟合得到其与Weber数及液相Reynolds数的关联式,预测值偏差大多在±30%内。

References

[1]  Wallis G B, One-dimensional two-phase flow [M]. New York: McGraw-Hill, 1969: 315-367
[2]  Groeneveld D C, Shan J Q, Vasi? A Z, Leung L K H, Durmayaz A, Yang J, Cheng S C, Tanase A, The 2006 CHF look-up table [J]. Nuclear Engineering and Design, 2007, 237(15-17): 1909-1922
[3]  Chen Xuejun(陈学俊). Basic of Two-phase Flow and Heat Transfer(气液两相流与传热基础)[M]. Chen Lixun(陈立勋), Zhou Fangde(周芳德). Beijing: Science Press, 1995: 136-138.
[4]  Whalley P B, Hutchinson P, Hewitt G F. Calculation of critical heat flux in forced convection boiling//Heat Trasfer. Proceedings of the 5th International Heat Transfer Conference[C]. United States: Atomic Energy Research Establishment, Harwell, 1974, 4: 290-294
[5]  Mishima K, Ishii M, Flow regime transition criteria for upward two-phase flow in vertical tubes [J]. Int. J. Heat Mass Transfer, 1984, 27(5): 723-737
[6]  Ishii M, Grolmes M A, Inception criteria for droplet entrainment in two-phase concurrent film flow [J]. AIChE Journal, 1975, 21(2): 308-318
[7]  Azzopardi B J, Drop sizes in annular two-phase flow. [J]. Experiments in Fluids, 1985, 3(1): 53-59
[8]  Ishii M, Mishima K, Droplet entrainment correlation in annular two-phase flow [J]. Int. J. Heat Mass Transfer, 1989, 32(10): 1835-1846
[9]  Okawa T, Kitahara T, Yoshida K, Matsumoto T, Kataoka I, New entrainment rate correlation in annular two-phase flow applicable to wide range of flow condition [J]. International Journal of Heat and Mass Transfer, 2002, 45(1): 87-98
[10]  Sawant P, Ishii M, Mori M, Prediction of amount of entrained droplets in vertical annular two-phase flow [J]. International Journal of Heat and Fluid Flow, 2009, 30(4): 715-728
[11]  Cioncolini A, Thome J R, Entrained liquid fraction prediction in adiabatic and evaporating annular two-phase flow [J]. Nuclear Engineering and Design, 2012, 243: 200-213
[12]  Utsuno H, Kaminaga F, Prediction of liquid film dryout in two-phase annular-mist flow in a uniformly heated narrow tube development of analytical method under BWR conditions [J]. Journal of Nuclear Science and Technology, 1998, 35(9): 643-653
[13]  Hewitt G F, Govan A H, Phenomenological modeling of non-equilibrium flows with phase change [J]. Int. J. Heat Mass Transfer, 1990, 33(2): 229-242
[14]  Okawa T, Kataoka I, Correlations for the mass transfer rate of droplets in vertical upward annular flow [J]. International Journal of Heat and Mass Transfer, 2005, 48(23-24): 4766-4778
[15]  Kataoka I, Ishii M, Nakayama A, Entrainment and deposition rates of droplets in annular two-phase flow [J]. International Journal of Heat and Mass Transfer, 2000, 43(9): 1573-1589
[16]  Okawa T, Murakami T, Takei R, Rate of droplet deposition in steam-water annular flow and effect of a flow obstacle [J]. Nuclear Engineering and Design, 2011, 241(11): 4497-4503
[17]  Saito T, Hughes E D, Carbon M W, Multi-fluid modeling of annular two-phase flow [J]. Nuclear Engineering and Design, 1978, 50(2): 225-271
[18]  Ahmad M, Chandraker D K, Hewitt G F, Vijayan P K, Walker S P, Phenomenological modeling of critical heat flux: The GRAMP code and its validation [J]. Nuclear Engineering and Design, 2013, 254: 280-290
[19]  Sugawara S, Droplet deposition and entrainment modeling based on the three-fluid model [J]. Nuclear Engineering and Design, 1990, 122(1-3): 67-84
[20]  Lee K-W, Baik S-J, Ro T-S, An utilization of liquid sublayer dryout mechanism in predicting critical heat flux under low pressure and low velocity conditions in round tubes [J]. Nuclear Engineering and Design, 2000,200(1-2): 69-81
[21]  Okawa T, Kotani A, Kataoka I, Naitoh M, Prediction of the critical heat flux in annular regime in various vertical channels [J]. Nucl. Eng. Des., 2004, 229(2-3): 223-236
[22]  Jiao B, Qiu L M, Lu J L, Gan Z H, Liquid film dryout model for predicting critical heat flux in annular two-phase flow [J]. Journal of Zhejiang University-Science A, 2009, 10(3): 398-417
[23]  Jiao Bo(焦波), Qiu Limin(邱利民), Lu Junliang(陆军亮), New correlation for entrainment fraction at onset of annular flow [J]. Journal of Chemical Industry and Engineering (China)(化工学报), 2008, 59(11):2750-2755
[24]  Groeneveld D C, Leung L K H, Kirillov P L, Bobkov V P, Smogalev I P, Vinogradov V N, Huang X C, Royer E, The 1995 look-up table for critical heat flux in tubes [J]. Nuclear Engineering and Design, 1996, 163(1-2):1-23

Full-Text

Contact Us

service@oalib.com

QQ:3279437679

WhatsApp +8615387084133