Flow and heat transfer characteristics of a nanofluid as the coolant in a typical MTR core
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Hesham F. Elbakhshawangy
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Abdelfatah Abdelmaksoud
Abstract
The purpose of this work was to perform a thermal–hydraulic numerical analysis of a nanofluid as the coolant in a typical MTR (material testing reactor) core. Numerical simulation was carried out for turbulent flow of water based nanofluid of different concentrations of Al2O3 nanoparticles through a sub-channel of a typical MTR core subjected to cosine shape heat flux at various values of Reynolds number using the Ansys-Fluent computer code. The optimum performance of the studied nanofluid as a coolant in MTR core was determined by the determination of the conditions under which the total entropy generation due to both heat transfer and fluid flow had a minimum value. The results showed that this condition was at Re = 4.8 × 104. The studied range of Reynolds number (Re) and particle concentration (ϕ) were 2.5 × 104 ≤ Re ≤ 5.6 × 104 and 0% ≤ ϕ ≤ 9% respectively. Results for local and average heat transfer and flow characteristics were presented. For the studied range of Reynolds number and particle concentration, four new correlations were developed. Two correlations relating Nusselt number and friction coefficient with the parameters Re and ϕ whereas the other two correlations were one relating Nusselt number with Reynolds and Prandtl numbers and the other relating the friction coefficient with Reynolds number.
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: None declared.
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Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
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Articles in the same Issue
- Frontmatter
- Single-phase flow heat transfer characteristics in helically coiled tube heat exchangers
- Design and optimization of an integrated gamma ray scanning system for the uranium sample
- Numerical simulation of the effect of rod bowing on critical heat flux
- Flow and heat transfer characteristics of a nanofluid as the coolant in a typical MTR core
- Mathematical modeling of point kinetic equations with temperature feedback for reactivity transient analysis in MTR
- An enhanced formalism for the inverse reactor kinetics problem
- The establishment of analysis methodology of NRCDose3 for Kuosheng nuclear power plant decommissioning
- Analysis of SMART reactor core with uranium mononitride for prolonged fuel cycle using OpenMC
- Conceptual design of an innovative I&XC fuel assembly for a SMR based on neutronic/thermal-hydraulic calculations at the BOC
- Optimized fractional-order PID controller based on nonlinear point kinetic model for VVER-1000 reactor
- High rate X-ray radiation shielding ability of cement-based composites incorporating strontium sulfate (SrSO4) minerals
- Vibration analysis for predictive maintenance and improved reliability of rotating machines in ETRR-2 research reactor
- Calendar of events
