Investigation of the nano fluid effects on heat transfer characteristics in nuclear reactors with dual cooled annular fuel using CFD (Computational Fluid Dynamics) modeling

Ebrahimian, M.; Ansarifar, G.R.

doi:10.1016/j.energy.2016.01.005

Cited by 32 publications

(8 citation statements)

References 12 publications

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“…To illustrate; Ebrahimian and Ansarifar (2016) investigated the thermal-hydraulic influences of nanofluid as coolant in a nuclear reactor with annular fuel. Their numerical analysis results showed that the heat transfer coefficient, i.e., hat transfer rate could be enhanced by nanoparticle utilization [4]. Mohammed et al, (2018) exhibited in their study that increasing nanoparticle concentration from 0% to 1% led vapor volume fraction and heat transfer coefficient to increase.…”

Section: Results For H-bn/dcm Nanofluidmentioning

confidence: 99%

“…Moreover, they observed that surface wettability for all nanoparticle sizes increased with the increase of the nanofluid concentration and slightly increased with the increase of nanoparticle size [3]. Ebrahimian and Ansarifar (2016) investigated numerically the nanofluid utilization as a coolant in a nuclear reactor. They used low concentration alumina nanoparticles containing nanofluid ranging from 0.001% to 0.05% in their analysis.…”

Section: Introductionmentioning

confidence: 99%

“…They observed a remarkable increment in the convection heat transfer coefficient because nanoparticle size became smaller and the volume fraction was increased [4]. Shoghl et al (2014) performed a numerical study on bubble dynamics in pool boiling of nanofluid with coated and Sodium Dodecyl Sulfonate (SDS) solution with different nanoparticles for mathematical modeling of bubbles in the boiling of deionized water.…”

Section: Introductionmentioning

confidence: 99%

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A Numerical Study on Performance Improvement in Boiling Heat Transfer via Dichloromethane-Based Nanofluid Utilization

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Section: Results For H-bn/dcm Nanofluidmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

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“…Nu , By combining Equations ( 2)-( 4) and reposition of Reynolds and Prandtl numbers, it can be written (5) where V is the speed of the coolant; ρ, and μ are its density, specific heat and dynamic coefficient of viscosity.…”

Section: Thermo-hydraulic Parametersmentioning

confidence: 99%

“…CFD is an effective and powerful tool to numerically simulate fluid flow and heat transfer [1,2]. In recent years, attempts were made to use CFD modeling in thermohydraulic design and investigations of nuclear reactors, especially Pressurized Water Reactors [3][4][5].…”

Section: Introductionmentioning

confidence: 99%

Thermo-Hydraulic Investigations of a Typical Small Modular PWR Using Computational Fluid Dynamics Modelling

Mirian

Ayoobian

2021

Therm. Eng.

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Computational Fluid Dynamics (CFD) is widely used in different industrial applications. In this research, the application of CFD in the thermo-hydraulic evaluation for a typical small modular Pressurized Water Reactor (PWR) was studied using ANSYS Fluent software. First, reactor core with different (pitchfuel rod diameter) was simulated using MCNP code. Subsequently, axial neutron heat flux was calculated in the hottest rod. In the following, different fuel channels were simulated using ANSYS workbench and corresponding mass flow rate according to the fluid outlet temperature was computed using Fluent. Then, thermohydraulic parameters including pumping power, convective heat transfer coefficient and turbulent intensity were calculated. Artificial neural network (ANN) coupled with genetic algorithm (GA) was used for optimization; and pair pitch -fuel rod diameter (0.012 m, 0.0072 m) was selected as the optimum value. Also, Critical Heat Flux (CHF) was computed with CFD-simulation, and compared with Tong CHF correlation and Groeneveld look-up table. A good agreement was observed between results, but CHF obtained from CFD simulation was more conservative. According to the results, Minimum Departure from Nucleate Boiling Ratio (MDNBR) was obtained as 2.12, which was compatible with its typical value. Accordingly, it could be concluded that the optimum reactor core was in the safe mode in the steady state conditions.

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Nanofluid applications in pressurized water reactors: A review

Mirian

Ansarifar

Esteki

2022

Intl J of Energy Research

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Summary The main purpose of this paper was to review nanofluid applications as the main coolant of pressurized water reactors (PWRs) with both solid and dual‐cooled annular fuel. In this regard, first, theoretical and experimental models for calculating thermo‐physical properties of nanofluids including density, specific heat, thermal conductivity, viscosity, and heat transfer coefficient were reviewed and the effects of different variables such as particle volume concentration, particle size, shape, and temperature on these parameters were determined. In the following, research related to neutronic, thermal‐hydraulic, and safety investigations of nanofluids as the main coolant of PWRs with solid and dual‐cooled annular fuel were reviewed. Corresponding methods, codes, and results were discussed and compared. Based on studies, it was concluded that nanofluids' effects on key neutronic parameters (keff, neutron flux and radial and axial power peaking factor) depend on the used nanoparticle, volume concentration, and nanoparticle deposition on the cladding, while nanofluids can increase heat transfer, critical heat flux, and minimum departure from nuclear boiling ratio (MDNBR). Also, it was found that nanofluids with low volume concentration in reactor core with dual‐cooled annular fuel can replicate the same advantages. Furthermore, using dual‐cooled annular fuel instead of solid fuel increases MDNBR margin and reduces coolant flow which leads to a more compact design of the reactor core and a reduction of capital cost. Finally, incoming challenges and future works were presented.

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Investigation of the nano fluid effects on heat transfer characteristics in nuclear reactors with dual cooled annular fuel using CFD (Computational Fluid Dynamics) modeling

Cited by 32 publications

References 12 publications

A Numerical Study on Performance Improvement in Boiling Heat Transfer via Dichloromethane-Based Nanofluid Utilization

A Numerical Study on Performance Improvement in Boiling Heat Transfer via Dichloromethane-Based Nanofluid Utilization

Thermo-Hydraulic Investigations of a Typical Small Modular PWR Using Computational Fluid Dynamics Modelling

Nanofluid applications in pressurized water reactors: A review

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