Prediction of a subcooled boiling flow with advanced two-phase flow models

Yun, Byong-Jo; Splawski, Andrew; Lo, Shih‐Ching; Song, Chul-Hwa

doi:10.1016/j.nucengdes.2011.08.067

Cited by 126 publications

(59 citation statements)

References 27 publications

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“…They used their data to develop a correlation for bubble lift-off diameter as a function of Jakob number and Prandtl number, which reproduces the data well at low wall superheat. Euh et al (2010) (Yeoh and Tu 2005, Yun et al 2010, Yun et al 2012, Wu et al 2008, Chen et al 2009). …”

Section: Previous Work and Motivationmentioning

confidence: 99%

“…This model was originally calibrated to predict bubble departure size in refrigerant R113 flow. Subsequently, modified and expanded the applicability of the Klausner's model for both horizontal and vertical channels under pool and flow boiling conditions with refrigerant R113, with pressure ranging from 20 to 280 kPa; Jakob number between 4 and 869; and gravity 1 to 0.014 g. Situ et al (2005) and Yeoh et al (2005) extended the model to flow conditions with water, and Yun et al (2010Yun et al ( , 2012 recently improved the model's predictive capability by incorporating a bubble condensation model as well as evaluating the model for a wider range of pressure, temperature, and flow rates.…”

Section: Previous Work and Motivationmentioning

confidence: 99%

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An experimental study of bubble departure diameter in subcooled flow boiling including the effects of orientation angle, subcooling, mass flux, heat flux, and pressure

Sugrue

Buongiorno

McKrell

2014

Nuclear Engineering and Design

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The effects of orientation angle, subcooling, heat flux, mass flux, and pressure on bubble departure diameter in the isolated bubble regime of subcooled flow boiling were studied by high-speed video in a two-phase flow loop that can accommodate a wide range of flow conditions. Specifically, the following ranges were explored: orientation angles of 0° (downward-facing horizontal), 30°, 45°, 60°, 90° (vertical) ). The combination of the test section design, high-speed video camera and LED lighting results in high accuracy (order of 20 microns) in the determination of the bubble departure diameter. The data indicate that the bubble departure diameter increases with increasing heat flux, decreasing mass flux, decreasing subcooling, and decreasing pressure. Also, the bubble departure diameter increases with decreasing orientation angle, i.e. the largest bubbles are found to detach from a downward-facing horizontal surface. The mechanistic bubble departure diameter model of Klausner et al. and its recent modification by Yun et al. were found to correctly predict all the observed parametric trends, but with large average errors and standard deviation: 65.5±75.8% for Klausner's and 37.9±51.2% for Yun's. Since the cube of the bubble departure diameter is used in subcooled flow boiling heat transfer models, such large errors are clearly unacceptable, and underscore the need for more accurate bubble departure diameter models.

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Section: Previous Work and Motivationmentioning

confidence: 99%

Section: Previous Work and Motivationmentioning

confidence: 99%

An experimental study of bubble departure diameter in subcooled flow boiling including the effects of orientation angle, subcooling, mass flux, heat flux, and pressure

Sugrue

Buongiorno

McKrell

2014

Nuclear Engineering and Design

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“…Methods to the more "mechanistic" determination of interfacial characteristics have also been proposed which include: Bubble number transport model -Riznic & Ishii [17], Guido-Lavalle et al [18]; Interfacial area transport model -Ishii et al [19] [6], Yao & Morel [20]; MUSIG (MUltiple-SIze-Group) population balance model -Yeoh et al [21] [22], Rzehak & Krepper [23]; Consortium for Advanced Simulation of LWRs S-bubble size distribution model -Yun et al [24] [25].…”

Section: Conservation Laws-based Models Of Two-phase Flowmentioning

confidence: 99%

“…The mechanistic models (by Klausner et al [42], Situ et al [43], Yun et al [24], etc.) are most complex and do not have closed-form solutions, but were found to be able to provide reasonably better predictions of the above-observed trends.…”

Section: 3)mentioning

confidence: 99%

Validation and Calibration of Nuclear Thermal Hydraulics Multiscale Multiphysics Models - Subcooled Flow Boiling Study

Bui¹,

Dinh²,

Williams³

2013

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A ABSTRACTIn addition to a validation data plan for quantification of data needs and strategy for data collection and characterization [1] [2], development of advanced techniques for calibration and validation of complex multiscale, multiphysics nuclear reactor simulation codes are a major component of the CASL VUQ plan.Advanced modeling of LWR systems normally involves a range of physicochemical models describing multiple interacting phenomena, such as thermal hydraulics, reactor physics, coolant chemistry, etc., which occur over a wide range of spatial and temporal scales. To a large extent, the accuracy of (and uncertainty in) overall model predictions is determined by the correctness of various sub-models, which are not conservation-laws based, but empirically derived from measurement data. Such sub-models normally require extensive calibration before the models can be applied to analysis of real reactor problems.This work demonstrates a case study of calibration of a common model of subcooled flow boiling, which is an important multiscale, multiphysics phenomenon in LWR thermal hydraulics. The calibration process is based on a new strategy of model-data integration, in which, all sub-models are simultaneously analyzed and calibrated using multiple sets of data of different types. Specifically, both data on large-scale distributions of void fraction and fluid temperature and data on smallscale physics of wall evaporation were simultaneously used in this work's calibration.In a departure from traditional (or common-sense) practice of tuning/calibrating complex models, a modern calibration technique based on statistical modeling and Bayesian inference was employed, which allowed simultaneous calibration of multiple sub-models (and related parameters) using different datasets. Quality of data (relevancy, scalability, and uncertainty) could be taken into consideration in the calibration process.This work presents a step forward in the development and realization of the CIPS Validation Data Plan [3] [1] at the Consortium for Advanced Simulation of LWRs to enable quantitative assessment of the CASL modeling of Crud-Induced Power Shift (CIPS) phenomenon, in particular, and the CASL advanced predictive capabilities, in general.This report is prepared for the Department of Energy's Consortium for Advanced Simulation of LWRs program's VUQ Focus Area. E EXECUTIVE SUMMARYThis milestone supports a case study of calibration and validation of a realistic and relatively complex subcooled flow boiling model, with the objective to develop recommendations on CASL-wide Model Calibration, Validation, and Uncertainty Quantification efforts. The SFB model utilized a common description of multiphase flow as inter-penetrating continua with conservation laws applied to each phase as a separate field. Small-scale physics related to thermal hydrodynamic inter-phase and flow-wall interactions were represented by various empirical/semi-empirical closure sub-models. In this SFB modeling, the sub-model of wall evaporation, which relied on...

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“…Similarly, the model has a good agreement with the low pressure experimental data. Byong [9] also indicated that the bubble size is an importance factor for accurately predicting the subcooled flow boiling, adopted a volumetric conserved bubble size model and introduced new wall boiling and two-phase logarithmic wall function models. The volumetric conserved bubble size model proposed by the population balance equation [10] considers the breakup and the coalescence based on pre-assumed lognormal bubble size distribution.…”

Section: Introductionmentioning

confidence: 99%

An Overall Bubble Diameter Model for the Flow Boiling and Numerical Analysis through Global Information Searching

Zhang

Lin

et al. 2018

Energies

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Bubble diameter is important for the three-dimensional nucleate boiling two-phase flow simulation. However, the bubble diameter is rarely considered as a variable because it is difficult to estimate. In this paper, a novel bubble diameter model is proposed for the boiling flow. The heat transfer growth, the breakup or coalescence of collision and the liquid impacting separation are considered as the factors affecting the bubble diameter, and three bubble diameter sub-models are developed to calculate the overall bubble diameter based on a departure diameter. In the model, the heat transfer growth is calculated after estimating the bubble location. The collision variation is deduced from the interfacial area concentration equation. The liquid impacting variation is calculated through phase interaction force and gas viscous force. The proposed model is conducted through global information searching in the flow boiling simulation and validated using the void fraction and temperature data from the literature. The effects of the heat transfer growth, the collision, and the separating volume on the bubble diameter are discussed.

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Prediction of a subcooled boiling flow with advanced two-phase flow models

Cited by 126 publications

References 27 publications

An experimental study of bubble departure diameter in subcooled flow boiling including the effects of orientation angle, subcooling, mass flux, heat flux, and pressure

An experimental study of bubble departure diameter in subcooled flow boiling including the effects of orientation angle, subcooling, mass flux, heat flux, and pressure

Validation and Calibration of Nuclear Thermal Hydraulics Multiscale Multiphysics Models - Subcooled Flow Boiling Study

An Overall Bubble Diameter Model for the Flow Boiling and Numerical Analysis through Global Information Searching

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