[1] |
FERNG Y M, CHANG H J. CFD investigating the impacts of changing operating conditions on the thermal-hydraulic characteristics in a steam generator[J]. Applied Thermal Engineering, 2008, 28(5):414-422.
|
[2] |
POLLOCK D T, YANG Z, WEN J T. Dryout avoidance control for multi-evaporator vapor compression cycle cooling[J]. Applied Energy, 2015, 160:266-285.
|
[3] |
BROMLEY L A. Heat transfer in stable film boiling[J]. Chem. Eng. Prog., 1950, 46:221.
|
[4] |
KOIZUMI Y, TASAKA K. Investigation of pre-and post-dryout heat transfer in upward steam-water two-phase flow at low flow rate[J]. Journal of Nuclear Science and Technology, 1982, 19(12):965-984.
|
[5] |
ANGHEL I G, ANGLART H, HEDBERG S. Experimental investigation of post-dryout heat transfer in annuli with flow obstacles[J]. Nuclear Engineering and Design, 2012, 246:82-90.
|
[6] |
ANGHEL I G, ANGLART H. Post-dryout heat transfer to high-pressure water flowing upward in vertical channels with various flow obstacles[J]. International Journal of Heat and Mass Transfer, 2012, 55(25):8020-8031.
|
[7] |
CHUNG Y J, BAE K H, KIM K K, et al. Boiling heat transfer and dryout in helically coiled tubes under different pressure conditions[J]. Annals of Nuclear Energy, 2014, 71:298-303.
|
[8] |
HWANG K W, KIM D E, YANG K H, et al. Experimental study of flow boiling heat transfer and dryout characteristics at low mass flux in helically-coiled tubes[J]. Nuclear Engineering and Design, 2014, 273:529-541.
|
[9] |
YANG S H, KIM S H, CHUNG Y J, et al. Experimental validation of the helical steam generator model in the TASS/SMR code[J]. Annals of Nuclear Energy, 2008, 35(1):49-59.
|
[10] |
WANG Z L, TIAN W X, WU Y W, et al. Numerical study on annular tube once-through steam generator using compressible flow model[J]. Annals of Nuclear Energy, 2012, 39(1):49-55.
|
[11] |
WANG Z L, TIAN W X, SU G H, et al. Development of a thermal hydraulic code for an integral reactor[J]. Progress in Nuclear Energy, 2013, 68:31-42.
|
[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[J]. International Journal of Heat and Mass Transfer, 2003, 46(25):4779-4788.
|
[13] |
JAYANTI S, VALETTE M. Prediction of dryout and post-dryout heat transfer at high pressures using a one-dimensional three-fluid model[J]. International Journal of Heat and Mass Transfer, 2004, 47(22):4895-4910.
|
[14] |
LI H, VASQUEZ S A, PUNEKAR H, et al. Prediction of boiling and critical heat flux using an eulerian multiphase boiling model[C]//ASME 2011 International Mechanical Engineering Congress and Exposition. Denver, Colorado, USA:American Society of Mechanical Engineers, 2011:463-476.
|
[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[J]. Nuclear Engineering and Design, 1996, 163(1):51-57.
|
[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[M]. America:The U.S. Nuclear Regulatory Commission, 1983:21-38.
|
[17] |
WEISMAN J, PEI B S. Prediction of critical heat flux in flow boiling at low qualities[J]. International Journal of Heat and Mass Transfer, 1983, 26(10):1463-1477.
|
[18] |
SUN B, YANG Y. Numerically investigating the influence of tube support plates on thermal-hydraulic characteristics in a steam generator[J]. Applied Thermal Engineering, 2012, 51(1):611-622.
|
[19] |
HOYER N. Calculation of dryout and post-dryout heat transfer for tube geometry[J]. International Journal of Multiphase Flow, 1998, 24(2):319-334.
|
[20] |
Babcock & Wilcox Company. Pressurized water reactor B&W technology crosstraining course manual[R]. America:The B & W Company, 2011.
|