Simulation of boiling flow in evaporator of separate type heat pipe with low heat flux

Kuang, Yiwu; Wang, Wen; Zhuan, Rui; Yi, Chongchong

doi:10.1016/j.anucene.2014.08.008

Cited by 38 publications

(8 citation statements)

References 24 publications

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“…Based on the CFD simulation, the Volume of Fluid (VOF) model is used and the condensation model proposed by previous researchers is used. 25 Ammonia is selected as the working fluid. The ammonia mass flux is 10 kg/(m 2 s) at the saturation temperature of 333.15 K (60 C).…”

Section: Flow Pattern In the Condensermentioning

confidence: 99%

“…In the two-phase flow section, the nucleate boiling has been proved to dominate the heat transfer, 25 Imura's correlation 37 is adopted to determine the flow boiling Nusselt number.…”

Section: Heat Transfer and Energy Conservationmentioning

confidence: 99%

“…23,24 Due to the heat pipe dimensions and low circulation flow rates, flow patterns and fluid distribution in largescale heat pipes differ from those in conventional ones. 25,26 It is necessary to get a deeper insight into the filling ratio effects on the thermal performance of the separate heat pipe. Motivated by this, the goal of this paper is to get a precise model to predict the large separate heat pipe heat transfer rate.…”

Section: Introductionmentioning

confidence: 99%

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Modeling and numerical investigation on the effects of filling ratio in a large separate heat pipe loop

Kuang

Wang

2021

Intl J of Energy Research

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Large separate heat pipe is a potential selection to establish the passive cooling system to remove decay heat from the Spent Fuel Pool. In this system, heat pipes are expected to work properly and effectively for a long time without human intervention. Due to the physical dimensions and structures, flow patterns, and fluid distribution in large-scale heat pipes differ from those in conventional ones. Based on the condensation flow patterns, a flow condensation model is presented. Then, a separate heat pipe model considering filling ratio effects is developed. Using the new model, the mean absolute errors of simulation are 5.5% (water), 5.1% (ammonia), and 4.3% (R134a). While in the conventional condensation model, these errors are 29.4%, 9.7%, and 10%. It is found

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Section: Flow Pattern In the Condensermentioning

confidence: 99%

“…In the two-phase flow section, the nucleate boiling has been proved to dominate the heat transfer, 25 Imura's correlation 37 is adopted to determine the flow boiling Nusselt number.…”

Section: Heat Transfer and Energy Conservationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Modeling and numerical investigation on the effects of filling ratio in a large separate heat pipe loop

Kuang

Wang

2021

Intl J of Energy Research

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“…Heat pipes offer high effective thermal conductivities (5000 -200,000 W.m -1 .K -1 ), energy-efficiency, light weight, low cost and the flexibility of many different size and shape options [2][3][4][5][6][7][8]. So, it can reduce the launch cost and the system mass.…”

Section: Introductionmentioning

confidence: 99%

“…Parametric studies of the influence of the PCM enclosure height and input/output heat transfer rates were discussed. Kuang et al [3] simulated the boiling flow in an evaporator of separate type heat pipe with low heat flux using a VOF multiphase flow model. The study on the heat transfer coefficient indicated that nucleate boiling is the dominant mechanism in large pipes at low mass and heat flux, with the heat transfer coefficient being less sensitive to the total mass flux.…”

Section: Introductionmentioning

confidence: 99%

Simulation of the Vapor-Liquid Two-Phase Flow of Evaporation and Condensation

Hong-jie¹,

Zhang²,

Li³

et al. 2016

IJHT

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The heat pipe receiver with integrated high temperature latent thermal energy storage is one of the key components of Solar Dynamic Space Power System (SDPSS), among which the evaporation and condensation is the main heat transfer mode, a very complicated two-phase flow. However, research on the two-phase flow and heat transfer characteristics is an effective way to improve the system efficiency and reduce the system mass. So a two-dimensional physical model was built and the volume of fluid (VOF) technique was used to model the interaction between the two phases. The UDF (Users Define Function) was introduced to handle the mass source terms. In the study, the relationship between superheat, subcooling and wall heat flux were investigated. In addition, the flow pattern of bubbles in the tube was analyzed. Compared with the churn bubbles flow, the heat transfer coefficient of the bubbles flow was much higher. Bubble departure diameter increased as surface subcooling increased. The work in this paper lays a good foundation for the further research on the heat transfer characteristics of heat pipe receiver with integrated high temperature latent thermal energy storage.

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Numerical Investigation and Machine Learning Predictions for Enhanced Thermal Management in Pulsating Heat Pipes: Modeling Turbulent Flow and Heat Transfer Characteristics in Nuclear Applications

Khosravian

2024

Numerical Methods in Fluids

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This paper presents a comprehensive numerical investigation of the performance of pulsating heat pipes (PHPs) within nuclear reactor cooling systems. A volume of fluid (VOF) method was used to simulate the complex multiphase flow, providing detailed insights into fluid distribution, phase interactions, and temperature variations under different operating conditions. The simulations revealed distinct phase separation and convective flow patterns that enhance heat transfer efficiency, which is critical for optimizing thermal management in nuclear reactors. Additionally, artificial neural network (ANN) models were employed to predict volume fractions and wall temperatures, achieving high accuracy with R2 values of 0.99 and 0.98, respectively, and low mean absolute errors (MAE). The ANN models also reduced computational time by 90% compared to traditional numerical simulations. These findings highlight the potential of PHPs to improve heat transfer in nuclear systems and demonstrate the practicality of ANN models for real‐time thermal optimization. The research contributes to enhancing the safety and efficiency of nuclear reactor cooling systems, with broader implications for thermal management across various engineering applications.

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Simulation of boiling flow in evaporator of separate type heat pipe with low heat flux

Cited by 38 publications

References 24 publications

Modeling and numerical investigation on the effects of filling ratio in a large separate heat pipe loop

Modeling and numerical investigation on the effects of filling ratio in a large separate heat pipe loop

Simulation of the Vapor-Liquid Two-Phase Flow of Evaporation and Condensation

Numerical Investigation and Machine Learning Predictions for Enhanced Thermal Management in Pulsating Heat Pipes: Modeling Turbulent Flow and Heat Transfer Characteristics in Nuclear Applications

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