Progress Toward Simulating Departure from Nucleate Boiling at High-Pressure Applications with Selected Wall Boiling Closures

被引:10
作者
Kim, Seung Jun [1 ]
Johns, Russell C. [1 ]
Yoo, Junsoo [2 ]
Baglietto, Emilio [3 ]
机构
[1] Los Alamos Natl Lab, POB 1663, Los Alamos, NM 87545 USA
[2] Idaho Natl Lab, 2525 Freemont Ave, Idaho Falls, ID USA
[3] MIT, 77 Massachusetts Ave, Cambridge, MA 02139 USA
关键词
Departure from nucleate boiling simulation; multiphase CFD; wall boiling closures; FLOW; BUBBLE;
D O I
10.1080/00295639.2020.1743579
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
Recently, a Eulerian-based two-fluid computational fluid dynamics (CFD) framework with a wall heat flux partitioning approach has been intensively investigated for departure from nucleate boiling (DNB) simulation under the U.S. Department of Energy-funded Consortium for Advanced Simulation of Light Water Reactors (CASL) program. Understanding of the DNB characteristics over a range of pressurized water reactor-like operating conditions and accurate prediction of boiling crisis in the nuclear power system have been grand challenges because of the large impact of DNB on reactor safety and operational economics. The ultimate goal of this task in the CASL program is to introduce a robust multiphase CFD-based DNB modeling framework that is capable of characterizing an entire boiling history in which the wall boiling mode experiences the following through multiple stages of heat transfer mode: (1) single-phase convective heat transfer, (2) nucleate boiling heat transfer, and (3) identification of the departure of nucleate boiling. To validate the CASL boiling model, we have benchmarked simulated DNB over three different flow channel configurations (pipe flow, 5 x 5 fuel bundle with mixing vane tests, and 5 x 5 fuel bundle without mixing vane tests) against experimental measurements, and the validation result with open literature is reported. The DNB detection criteria in the simulation are checked by monitoring the peak wall temperature, wall dryout factor, and net energy balance. In addition to the DNB performance test, some preliminary sensitivity results on closure model selection are reported to address the prediction capability of local void profile against measurements. The boiling simulation tested in this study exhibits a maximum deviation of 24% from the measured DNB value in a high-pressure (i.e., 138 bars) subcooled pipe flow test. The ranges of operating conditions are as follows: 1650 to 2650 kg/m(2)center dot s for mass flux and 8.5 to 96 K for subcooled inlet temperature. The deviation is even reduced to 7% when the subcooled temperature is less than 40 K. Besides accuracy, base practice guidelines for DNB detection criteria are tested by monitoring three simulation variables: (1) maximum wall temperature, (2) wall dryout factor (i.e., K-value), and (3) energy balance. Numerical robustness of DNB simulation is largely achieved in most of the validation test except for a few high subcooled test cases.
引用
收藏
页码:690 / 707
页数:18
相关论文
共 29 条
[1]  
[Anonymous], 2018, SIEMENS START CCM VE
[2]  
Bartolemei G.G., 1967, THERM ENG, V14, P123
[3]  
BARTOLOMEI GG, 1982, THERM ENG+, V29, P132
[4]  
Brewster R., 2019, IND APPL CASL DNB ME
[5]  
Chawta J., 1977, HEAT TRANSFER BOILIN, V237, P247
[6]   A PHOTOGRAPHIC STUDY OF POOL BOILING IN THE REGION OF THE CRITICAL HEAT FLUX [J].
COLE, R .
AICHE JOURNAL, 1960, 6 (04) :533-538
[7]  
Cooper J., 2007, International Association for the Properties of Water and Steam
[8]   Active nucleation site density in boiling systems [J].
Hibiki, T ;
Ishii, M .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2003, 46 (14) :2587-2601
[9]  
KIM S. J., 2016, LAUR1628815
[10]  
KIM S. J., 2019, LAUR1928666