Visualization of the subcooled flow boiling of R-134a in a vertical rectangular channel with an electrically heated wall

Bang, In Cheol; Chang, Soon Heung; Baek, Won-Pil

doi:10.1016/j.ijheatmasstransfer.2004.04.030

Cited by 54 publications

(16 citation statements)

References 12 publications

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“…9, which shows that the instantaneous temperature of the microheater dropped from 140.3 to 133.5°C during OMEB and increased again during the refilling of the superheated liquid. The instantaneous temperature drop during MEB in subcooled flow boiling is similar to that during the onset of nucleation in subcooled flow boiling [4,5]. In addition, it can be seen from Fig.…”

Section: Onset Of Microbubble Emission Boilingsupporting

confidence: 63%

“…As early as in 1934, Nukiyama [1] had studied subcooled pool boiling of water about a heated wire at a superheated temperature, and reported the first boiling curve in terms of heat flux versus degree of wall superheat. For the past several decades, subcooled flow boiling in channels has also attracted considerable attention [2][3][4][5][6][7] because of its applications in nuclear reactor cores, lasers, as well as vehicle power electronics, where the high-heat-flux cooling is required. Kandlikar [2] divided subcooled flow boiling of water into partial boiling, fullydeveloped boiling, and significant void flow regions, and a comprehensive methodology with appropriate correlations was presented to predict the heat transfer in each region.…”

Section: Introductionmentioning

confidence: 99%

“…A semi-empirical correlation for determining the variation of bubble size and lifetime was proposed. Subcooled flow boiling heat transfer and bubble characteristics of R-134a were investigated in a number of papers [4][5][6]. However, the effects of mass flux and liquid subcooling on the onset of nucleate boiling (ONB) reported in these papers were not consistent.…”

Section: Introductionmentioning

confidence: 99%

“…According to this hypothesis, both high degree of subcooling and high heat flux are important factors for MEB generation. The reasons why MEB was not frequently observed in subcooled flow boiling experiments in the past [2][3][4][5][6] might be attributed to the following reasons: (i) the simultaneous conditions of high heat flux and high degree of subcooling were not satisfied in most of the flow boiling experiments which were usually carried out in a long tube heated uniformly with a heat flux less than 1 MW/m 2 ; (ii) if the imposed heat flux on the wall was high enough to initiate MEB in the upstream, the wall downstream would be burnout. Furthermore, since liquid subcooling was decreasing along the flow direction due to the uniform heating, there was insufficient subcooling to sustain MEB in the downstream even if no burnout occurred; and (iii) no high-speed camera and microscope were used to observe flow boiling in these large heated tubes in the past.…”

Section: Introductionmentioning

confidence: 99%

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Subcooled flow boiling and microbubble emission boiling phenomena in a partially heated microchannel

Wang

Cheng

2009

International Journal of Heat and Mass Transfer

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Section: Onset Of Microbubble Emission Boilingsupporting

confidence: 63%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Subcooled flow boiling and microbubble emission boiling phenomena in a partially heated microchannel

Wang

Cheng

2009

International Journal of Heat and Mass Transfer

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“…Bang et al (2004) Visual bubble 1 (R134a) Situ et al (2004a,b) Bubble dynamics 1 (1 atm) Unal (1976) Bubble growth 3 (full P) Chang et al (2002) Wall bubble 1 (R134a) Basu et al (2005) Wall heat partitioning in SFB 1 (low P) Basu et al (2002) Boiling onset, nucleation site density 1 (low P) Nucleation site …”

Section: Authors (Year)mentioning

confidence: 99%

CIPS Validation Data Plan

Dinh¹

2012

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The Consortium for Advanced Simulation of Light Water Reactors (CASL) Program is a multi-institutional effort to develop and apply advance modeling and simulation (AMS) capabilities to the engineering analysis, design, and licensing of nuclear energy systems. One of CASL's tasks is to create AMS tools to accurately predict the extent and effect of crud deposits on nuclear power plants (i.e., crud-induced power shift). The current capabilities are derived from a series of codes, some mature industry products and some recently initiated by CASL. While there are many seemingly relevant experiments and measurement data, a close examination reveals that very few experiments and data are directly relevant to high-fidelity mechanistic models and the data are not compatible with modern verification, validation, and uncertainty quantification (VUQ) methods. In addition, because of long lead times and a lack of resources, only limited new data are expected over the next 3 to 5 years. This report documents the analysis, findings, and recommendations for developing a validation data plan to effectively deal with the severe lack and low quality of validation data. The study suggests a pragmatic approach whose near-term focus is support for the development of advanced capability in Virtual Environment for Reactor Applications. An application-oriented VUQ-guided data assimilation framework is envisioned as a means to integrate heterogeneous data to achieve uncertainty reduction. The study also identifies technical areas where further development in VUQ methods and tools are needed.This report is prepared for the Department of Energy's Consortium for Advanced Simulation of LWRs (CASL) program's VUQ Focus Area under activity VUQ.VVDA.P4.02 entitled "Validation Data Planning for CIPS". CIPS Validation Data PlanDinh, INL-EXT-12-25347 6 SUMMARYThe Consortium for Advanced Simulation of Light Water Reactors (CASL) Program is a leading multi-institutional effort supported by the U.S. Department of Energy to develop and apply advanced modeling and simulation capability to create a virtual environment for predictive simulation of light water reactors (LWRs). The virtual reactor simulation is built on so-called Virtual Environment for Reactor Applications (VERA). The baseline capability (VERA-BL) comprises state-of-the-practice simulation codes made available to CASL by its industry partners. From this, the CASL researchers will use state-of-the-art methods and tools in nuclear fuel and material modeling, computational fluid dynamics and computational structural mechanics, radiation transport, computer and computational science, and verification, validation, and uncertainty quantification (VUQ) to develop advanced multi-physics, multi-scale, high-fidelity simulation capability or VERA advanced capability (VERA-AC). VERA-AC is envisioned to be based on more mechanistic coupled treatment of the physical processes at much higher resolutions than VERA-BL, and will subsequently be computationally intense and require solutions on moder...

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CFD Modeling of Critical Heat Flux in Nuclear Fuel Pins

Vadlamudi,

Nayak

2023

Handbook of Multiphase Flow Science and Technology

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Visualization of the subcooled flow boiling of R-134a in a vertical rectangular channel with an electrically heated wall

Cited by 54 publications

References 12 publications

Subcooled flow boiling and microbubble emission boiling phenomena in a partially heated microchannel

Subcooled flow boiling and microbubble emission boiling phenomena in a partially heated microchannel

CIPS Validation Data Plan

CFD Modeling of Critical Heat Flux in Nuclear Fuel Pins

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