Improved Heat Transfer Capabilities of Nanofluids—An Assessment Through CFD Analysis
Authors:
Open Access
- 17 September 2024
- journal article
- research article
- Published by Wiley in Chemical Engineering & Technology
- Vol. 47 (11)
Abstract
Conventional fluids used in fission‐based water‐cooled nuclear reactors have lower heat transfer coefficients (HTCs) and thermal conductivity, which has led researchers to explore high‐performance fluids that can enhance heat transfer in routine operation and prevent core meltdown in the case of accidents. It is important to investigate a wide range of fluids that can help designers improve thermal hydraulic characteristics, such as HTC, critical heat flux, and minimum departure from nucleate boiling ratio (MDNBR). In this study, the effectiveness of nanofluids in enhancing heat transfer parameters, including thermal conductivity and heat capacity, was investigated. Four different nanofluids (Al2O3–H2O, ZrO2–H2O, Ag–H2O, and Si–H2O) with pure water as the primary coolant in an HPR‐1000 nuclear reactor were compared using computational methods. Due to computational limitations, only the flow channel among four fuel rods with the highest power density in the core was simulated using Eulerian computational fluid dynamics. The results of this study show that silver water (Ag–H2O) nanofluid outperformed other nanofluids and pure water. It had a higher average HTC and MDNBR, with a 67.15 % and 45.23 % improvement, respectively, compared to pure water. The fuel rod wall temperature was also reduced by 28.5 K with Ag–H2O compared to water. Comparison of current simulated results with literature data shows a good agreement.Keywords
This publication has 30 references indexed in Scilit:
- Solidification of nano-enhanced PCM-porous composites in a cylindrical cold thermal energy storage enclosureCase Studies in Thermal Engineering, 2022
- Evaluation of nanofluid coolant effects on VVER-1000/V-446 reactor using 3-D full core coupled neutronic and thermohydraulics analysisAnnals of Nuclear Energy, 2021
- On the performance of nanofluids in APR 1400 PLUS7 assembly: NeutronicsAnnals of Nuclear Energy, 2020
- Assessment of the nano-fluid effects on the thermal reactivity feedback coefficients in the VVER-1000 nuclear reactor with nano-fluid as a coolant using thermal hydraulic and neutronics analysisAnnals of Nuclear Energy, 2019
- Twofold application of nanofluids as the primary coolant and reactivity controller in a PWR reactor: Case study VVER-1000 in normal operationAnnals of Nuclear Energy, 2016
- Supercritical water heat transfer for nuclear reactor applications: A reviewAnnals of Nuclear Energy, 2016
- Design and neutronic investigation of the Nano fluids application to VVER-1000 nuclear reactor with dual cooled annular fuelAnnals of Nuclear Energy, 2016
- Nanofluid application in post SB-LOCA transient in VVER-1000 NPPAnnals of Nuclear Energy, 2015
- Coupled neutronic/thermo-hydraulic analysis of water/Al2O3 nanofluids in a VVER-1000 reactorAnnals of Nuclear Energy, 2014
- Subchannel analysis of nanofluids application to VVER-1000 reactorChemical Engineering Research and Design, 2013