Experimental and numerical analysis of heat transfer from main vessel to safety vessel using h2o/al2o3 nanofluid in a nuclear reactor vault

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Abstract

Nuclear reactor produces electricity by fission reaction of uranium and neutron. Due to this reaction, a lot of heat energy is produced. Hence, this must be kept under control or else the components of reactor core may get damaged which in turn leads to radiation leakage which affect the surrounding environment. Ever since nuclear plants came into operation, dissipation of heat is done by water. But some inert gases that have good heat transfer coefficient and good thermal conductivity for heat dissipation process. The ultimate aim of this project is to find out how efficiently a nanofluid and argon gas can dissipate heat from the reactor vault as a coolant in a circuit. The most commonly used nanofluid is Al2O3 nanoparticle with water or ethylene as base fluid. Al2O3 has good thermal properties and it is easily available. In addition, it can be stabilized at various pH levels. The various temperature distribution leads to different characteristic curves and the characteristic curves give detailed report to enhance heat transfer rate from main vessel to safety vessel. The nanofluid used for the heat transfer process is a combination of Al2O3 (nanoparticle) and therminol 55 (base fluid). The alumina nanoparticle is mixed with therminol 55 at 0.01 vol% concentration. Formerly, the experiments have been conducted by using water and nitrogen gas this leads to poor heat transfer rate. We alternatively conducted this experiment by using nanofluid and argon gas for nurturing the heat transfer rate.

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Anish, M., Kanimozhi, B., Beemkumar, N., & Jayaprapakar, J. (2018). Experimental and numerical analysis of heat transfer from main vessel to safety vessel using h2o/al2o3 nanofluid in a nuclear reactor vault. Desalination and Water Treatment, 114, 135–145. https://doi.org/10.5004/dwt.2018.22384

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