THERMAL SCIENCE

International Scientific Journal

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Maria Anish

,

Balakrishnan Kanimozhi

EXPERIMENTAL STUDY OF HEAT TRANSFER THROUGH COOLING WATER CIRCUIT IN A REACTOR VAULT BY USING AL2O3 NANOFLUID

ABSTRACT
The heat produced in the nuclear reactor due to fission reaction must be kept in control or else it will damage the components in the reactor core. Nuclear plants are using water for the operation dissipation of heat. Instead, some chemical substances which have higher heat transfer coefficient and high thermal conductivity. This experiment aims to find out how efficiently a Nano fluid can dissipate heat from the reactor vault. The most commonly used Nano fluid is Al2O3 Nano particle with water or ethylene as base fluid. Al2O3 has good thermal property and it is easily available. In addition, it can be stabilized in various PH levels. The Nano fluid is fed into the reactor’s coolant circuit. The various temperature distribution leads to different characteristic curve that occurs on various valve condition leading to a detailed study on how temperature distribution carries throughout the cooling circuit. As a combination of Al2O3 as a Nano particle and therminol 55 as base fluid are used for the heat transfer process. The alumina nanoparticle is mixed in therminol 55 at 0.05% vol. concentration. Numerical analysis on the Reactor Vault model was carried out by using ABAQUS and the experimental results were compared with numerical results.
KEYWORDS
Al2O3 nanoparticles, convective radiation, heat dissipation, therminol, nuclear reactor, inert gases, nanofluids, sonification, reactive plates
PAPER SUBMITTED: 2017-05-27
PAPER REVISED: 2017-09-07
PAPER ACCEPTED: 2017-09-25
PUBLISHED ONLINE: 2017-10-07
DOI REFERENCE: https://doi.org/10.2298/TSCI170527207A
CITATION EXPORT: view in browser or download as text file
THERMAL SCIENCE YEAR 2018, VOLUME 22, ISSUE Issue 2, PAGES [1149 - 1161]
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Experimental study of heat transfer through cooling water circuit in a reactor vault by using Al2O3 nanofluid

© 2024 Society of Thermal Engineers of Serbia. Published by the Vinča Institute of Nuclear Sciences, National Institute of the Republic of Serbia, Belgrade, Serbia. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution-NonCommercial-NoDerivs 4.0 International licence