Multi-Scale Modeling and Analysis of Convective Boiling: Towards the Prediction of CHF in Rod Bundles

Ničeno, Bojan; SATO, Yuriko; Badillo, Arnoldo; Andreani, Michele

doi:10.5516/net.2010.42.6.620

Cited by 14 publications

(8 citation statements)

References 41 publications

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“…Single or multiple bubble rising flows have been studied in the past years by numerical analysis and experiments [9][10][11][12][13][14][15][16][17][18]. Bhaga and Weber [11] performed extensive experiments about single bubble rising in liquids and reported a flow regime map that was correlated with dimensionless variables like Eotvos, Morton, and Reynolds numbers.…”

Section: Introductionmentioning

confidence: 99%

“…For multiple bubbles, Brereton and Korotney [13] have reported the characteristics of the coalescence of two rising bubbles at different positions through visual experiments. Numerical simulations of coaxial and oblique coalescence have been carried out by several researchers [14][15][16][17]. Although many numerical calculations have been done, the results for identical flow conditions were not consistent owing to the numerical schemes and initial assumptions, including boundary conditions.…”

Section: Introductionmentioning

confidence: 99%

“…Two bubbles, which have the same diameter of d = 40, were initially positioned either inline or staggered, as shown in Figs. 11 and 14, at t=0 [13,15,17]. In Fig.…”

mentioning

confidence: 99%

“…This phenomenon is difficult to simulate because of the topological change. The interface tracking method, which transforms the grid along the interface, is especially difficult to solve; however, the interface capturing methods such as the VOF method and the LBM can be done successfully [16,17].…”

mentioning

confidence: 99%

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A Comparative Study of Lattice Boltzmann and Volume of Fluid Method for Two-Dimensional Multiphase Flows

Ryu¹,

Ko²

2012

Nuclear Engineering and Technology

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

“…Two bubbles, which have the same diameter of d = 40, were initially positioned either inline or staggered, as shown in Figs. 11 and 14, at t=0 [13,15,17]. In Fig.…”

mentioning

confidence: 99%

mentioning

confidence: 99%

See 2 more Smart Citations

A Comparative Study of Lattice Boltzmann and Volume of Fluid Method for Two-Dimensional Multiphase Flows

Ryu¹,

Ko²

2012

Nuclear Engineering and Technology

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“…The NEPTUNE-CFD and TRIO-U codes are two-phase codes at mesoscale and microscale, respectively. The MSMA project focuses on multiscale modeling and analysis of convective boiling, which ultimately aims at the predictive capability of critical heat flux [8]. The ACE-3D code, which can be categorized into a mesoscale code, adopts an advanced model by combining a twofluid model and an interface tracking method [9].…”

Section: Introductionmentioning

confidence: 99%

The Cupid Code Development and Assessment Strategy

Jeong¹,

Yoon²,

Park³

et al. 2010

Nuclear Engineering and Technology

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The multiscale thermal‐hydraulic simulation for nuclear reactors: A classification of the coupling approaches and a review of the coupled codes

Zhang

2020

Int J Energy Res

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Summary Simulation is becoming increasingly important in the safety analysis of nuclear reactors nowadays. The physical phenomena in a nuclear power plant happen on three classified scales: system scale (phenomenon over the whole plant is concerned), component scale (phenomenon in specific component is concerned), and mesoscale (phenomenon in a small part of a component is concerned). Owing to the particular emphases, various codes are developed to simulate particular problems. System codes intend to predict the behavior of the whole power plant during normal or accidental phases (system scale). Subchannel codes are for core behavior predictions (component scale). CFD codes can simulate the thermal‐hydraulic in a fixed part of the plant (mesoscale). Those codes are coupled together to better predict the conditions in a nuclear reactor in last the two decades, which is the multiscale thermal‐hydraulic simulation approach for nuclear power systems. Diverse coupling approaches are developed and various coupling codes are implemented. This paper first proposes a classification of those approaches. It tells that a multiscale coupling is composed of five items: coupling architecture, operation mode, domain coupling, field mapping, and temporal coupling. Numbers of options are available for each item. For coupling architecture, it can be internal coupling, via‐IO coupling, server‐client, or serverless coupling. For operation mode, it can be either parallel or serial. For domain coupling, it can be either domain‐decomposition or domain‐overlapping coupling. For field mapping, it can be manual‐definition, processed by user‐developing toolkit, or handled by third‐party libraries. For temporal coupling, it can be explicit coupling, semi‐implicit coupling, or implicit coupling. An evaluation of the approaches is performed based on new‐proposed criterion. A general review of the multiscale thermal‐hydraulic coupled codes is made based on the classification. Especially, a review of the domain‐overlapping approach is present considering it is the most promising but challenging method for multiscale thermal‐hydraulic simulation.

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Multi-Scale Modeling and Analysis of Convective Boiling: Towards the Prediction of CHF in Rod Bundles

Cited by 14 publications

References 41 publications

A Comparative Study of Lattice Boltzmann and Volume of Fluid Method for Two-Dimensional Multiphase Flows

A Comparative Study of Lattice Boltzmann and Volume of Fluid Method for Two-Dimensional Multiphase Flows

The Cupid Code Development and Assessment Strategy

The multiscale thermal‐hydraulic simulation for nuclear reactors: A classification of the coupling approaches and a review of the coupled codes

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