Correlation Equations of Heat Transfer in Nanofluid Al2O3-Water as Cooling Fluid in a Rectangular Sub Channel Based CFD Code

Safety is a major concern in the design, operation and development of a nuclear reactor. One aspect of nuclear reactor safety factor is thermal-hydraulics aspect. In a PWR-type nuclear power plant has been used lighter fluid coolant is water or H2O. In this research, using nanofluid Al2O3-Water with...

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Main Authors: Anwar Ilmar Ramadhan, As Natio Lasman, Anggoro Septilarso
Format: Article
Language:English
Published: Diponegoro University 2015-04-01
Series:International Journal of Science and Engineering
Subjects:
CFD
Online Access:https://ejournal.undip.ac.id/index.php/ijse/article/view/8316
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spelling doaj-a0b1c6f7178a40a88bf14d963f7c31722020-11-24T21:59:46ZengDiponegoro UniversityInternational Journal of Science and Engineering 2086-50232302-57432015-04-018212012410.12777/ijse.8.2.120-1247202Correlation Equations of Heat Transfer in Nanofluid Al2O3-Water as Cooling Fluid in a Rectangular Sub Channel Based CFD CodeAnwar Ilmar Ramadhan0As Natio Lasman1Anggoro Septilarso2University of Muhammadiyah JakartaNuclear Energy Regulatory Agency (BAPETEN) Republic of IndonesiaNuclear Energy Regulatory Agency (BAPETEN) Republic of IndonesiaSafety is a major concern in the design, operation and development of a nuclear reactor. One aspect of nuclear reactor safety factor is thermal-hydraulics aspect. In a PWR-type nuclear power plant has been used lighter fluid coolant is water or H2O. In this research, using nanofluid Al2O3-Water with volume fraction of (1%), (2%) and also (3%), used as a cooling fluid in a nuclear reactor core with sub channel PWR fuel element rectangular arrangement. This research was carried out modeling of fuel elements are arranged rectangular, then performed numerical simulations using Computational Fluid Dynamics (CFD) code. In order to obtain the characteristic pattern of flow velocity of each fluid, the fluid temperature distribution along the cylinder wall temperature distribution of the fuel element. Then analyzed the heat transfer in a nuclear reactor core with sub channel PWR fuel element rectangular arrangement, including heat transfer coefficient, Nusselt number (Nu), as well as heat transfer correlations. Heat transfer correlation for nanofluid Al2O3-Water (1%), (2%) and also (3%) proved to core of PWR nuclear reactor fuel element sub channel rectangular arrangement with the Reynolds number (Re) is stretched, namely: 404 096 <Re <423 084 and with constant heat flux is 2600 W / m2, and the composition ratio (pitch / diameter) 1.33.https://ejournal.undip.ac.id/index.php/ijse/article/view/8316NanofluidSub ChannelHeat TransferPressurized Water ReactorCFD
collection DOAJ
language English
format Article
sources DOAJ
author Anwar Ilmar Ramadhan
As Natio Lasman
Anggoro Septilarso
spellingShingle Anwar Ilmar Ramadhan
As Natio Lasman
Anggoro Septilarso
Correlation Equations of Heat Transfer in Nanofluid Al2O3-Water as Cooling Fluid in a Rectangular Sub Channel Based CFD Code
International Journal of Science and Engineering
Nanofluid
Sub Channel
Heat Transfer
Pressurized Water Reactor
CFD
author_facet Anwar Ilmar Ramadhan
As Natio Lasman
Anggoro Septilarso
author_sort Anwar Ilmar Ramadhan
title Correlation Equations of Heat Transfer in Nanofluid Al2O3-Water as Cooling Fluid in a Rectangular Sub Channel Based CFD Code
title_short Correlation Equations of Heat Transfer in Nanofluid Al2O3-Water as Cooling Fluid in a Rectangular Sub Channel Based CFD Code
title_full Correlation Equations of Heat Transfer in Nanofluid Al2O3-Water as Cooling Fluid in a Rectangular Sub Channel Based CFD Code
title_fullStr Correlation Equations of Heat Transfer in Nanofluid Al2O3-Water as Cooling Fluid in a Rectangular Sub Channel Based CFD Code
title_full_unstemmed Correlation Equations of Heat Transfer in Nanofluid Al2O3-Water as Cooling Fluid in a Rectangular Sub Channel Based CFD Code
title_sort correlation equations of heat transfer in nanofluid al2o3-water as cooling fluid in a rectangular sub channel based cfd code
publisher Diponegoro University
series International Journal of Science and Engineering
issn 2086-5023
2302-5743
publishDate 2015-04-01
description Safety is a major concern in the design, operation and development of a nuclear reactor. One aspect of nuclear reactor safety factor is thermal-hydraulics aspect. In a PWR-type nuclear power plant has been used lighter fluid coolant is water or H2O. In this research, using nanofluid Al2O3-Water with volume fraction of (1%), (2%) and also (3%), used as a cooling fluid in a nuclear reactor core with sub channel PWR fuel element rectangular arrangement. This research was carried out modeling of fuel elements are arranged rectangular, then performed numerical simulations using Computational Fluid Dynamics (CFD) code. In order to obtain the characteristic pattern of flow velocity of each fluid, the fluid temperature distribution along the cylinder wall temperature distribution of the fuel element. Then analyzed the heat transfer in a nuclear reactor core with sub channel PWR fuel element rectangular arrangement, including heat transfer coefficient, Nusselt number (Nu), as well as heat transfer correlations. Heat transfer correlation for nanofluid Al2O3-Water (1%), (2%) and also (3%) proved to core of PWR nuclear reactor fuel element sub channel rectangular arrangement with the Reynolds number (Re) is stretched, namely: 404 096 <Re <423 084 and with constant heat flux is 2600 W / m2, and the composition ratio (pitch / diameter) 1.33.
topic Nanofluid
Sub Channel
Heat Transfer
Pressurized Water Reactor
CFD
url https://ejournal.undip.ac.id/index.php/ijse/article/view/8316
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