Neutronic simulation of a CANDU-6 reactor with heavy water-based nanofluid coolant
In recent years, extended studies are developed for investigation the effects of using nanofluids in NPP as coolant. CANDU-6 reactors have the potential to use nanofluid coolants because in these reactors, the moderator system is fully independent of the primary heat transport system. MCNPX...
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Format: | Article |
Language: | English |
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VINCA Institute of Nuclear Sciences
2017-01-01
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Series: | Nuclear Technology and Radiation Protection |
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Online Access: | http://www.doiserbia.nb.rs/img/doi/1451-3994/2017/1451-39941704320M.pdf |
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author | Mirghaffari Reza Jahanfarnia Gholamreza Athari Allaf Mitra |
author_facet | Mirghaffari Reza Jahanfarnia Gholamreza Athari Allaf Mitra |
author_sort | Mirghaffari Reza |
collection | DOAJ |
description | In recent years, extended studies are developed for investigation the effects
of using nanofluids in NPP as coolant. CANDU-6 reactors have the potential to
use nanofluid coolants because in these reactors, the moderator system is
fully independent of the primary heat transport system. MCNPX code has been
used for modelling and simulation of a CANDU-6 reactor containing a nanofluid
as primary coolant. The variation of multiplication factor and total neutron
flux distribution along a fuel channel, next to the central axis, has been
investigated by using different nanofluids. In this analysis, heavy
water-based nanofluids containing various volumetric percentages of Al2O3,
TiO2, CuO, Ti, Cu, Zr, and Si nanoparticles were used. A typical CANDU-6
reactor was selected as reference for reactor core modelling. The results of
the neutronic analysis show that Al2O3 nanofluids with 1% volumetric
percentage are the most suitable coolant for CANDU-6 reactors which can
increase the coolant heat transfer coefficient and consequently enhance the
plant efficiency. |
first_indexed | 2024-04-12T13:21:12Z |
format | Article |
id | doaj.art-ed2f39f2a5fe4042acf59219e12cd52c |
institution | Directory Open Access Journal |
issn | 1451-3994 1452-8185 |
language | English |
last_indexed | 2024-04-12T13:21:12Z |
publishDate | 2017-01-01 |
publisher | VINCA Institute of Nuclear Sciences |
record_format | Article |
series | Nuclear Technology and Radiation Protection |
spelling | doaj.art-ed2f39f2a5fe4042acf59219e12cd52c2022-12-22T03:31:29ZengVINCA Institute of Nuclear SciencesNuclear Technology and Radiation Protection1451-39941452-81852017-01-0132432032610.2298/NTRP1704320M1451-39941704320MNeutronic simulation of a CANDU-6 reactor with heavy water-based nanofluid coolantMirghaffari Reza0Jahanfarnia Gholamreza1Athari Allaf Mitra2Islamic Azad University, Science and Research Branch, Department of Nuclear Engineering, Tehran, IranIslamic Azad University, Science and Research Branch, Department of Nuclear Engineering, Tehran, IranIslamic Azad University, Science and Research Branch, Department of Nuclear Engineering, Tehran, IranIn recent years, extended studies are developed for investigation the effects of using nanofluids in NPP as coolant. CANDU-6 reactors have the potential to use nanofluid coolants because in these reactors, the moderator system is fully independent of the primary heat transport system. MCNPX code has been used for modelling and simulation of a CANDU-6 reactor containing a nanofluid as primary coolant. The variation of multiplication factor and total neutron flux distribution along a fuel channel, next to the central axis, has been investigated by using different nanofluids. In this analysis, heavy water-based nanofluids containing various volumetric percentages of Al2O3, TiO2, CuO, Ti, Cu, Zr, and Si nanoparticles were used. A typical CANDU-6 reactor was selected as reference for reactor core modelling. The results of the neutronic analysis show that Al2O3 nanofluids with 1% volumetric percentage are the most suitable coolant for CANDU-6 reactors which can increase the coolant heat transfer coefficient and consequently enhance the plant efficiency.http://www.doiserbia.nb.rs/img/doi/1451-3994/2017/1451-39941704320M.pdfnanofluidCANDU-6MCNPXneutronic analysis |
spellingShingle | Mirghaffari Reza Jahanfarnia Gholamreza Athari Allaf Mitra Neutronic simulation of a CANDU-6 reactor with heavy water-based nanofluid coolant Nuclear Technology and Radiation Protection nanofluid CANDU-6 MCNPX neutronic analysis |
title | Neutronic simulation of a CANDU-6 reactor with heavy water-based nanofluid coolant |
title_full | Neutronic simulation of a CANDU-6 reactor with heavy water-based nanofluid coolant |
title_fullStr | Neutronic simulation of a CANDU-6 reactor with heavy water-based nanofluid coolant |
title_full_unstemmed | Neutronic simulation of a CANDU-6 reactor with heavy water-based nanofluid coolant |
title_short | Neutronic simulation of a CANDU-6 reactor with heavy water-based nanofluid coolant |
title_sort | neutronic simulation of a candu 6 reactor with heavy water based nanofluid coolant |
topic | nanofluid CANDU-6 MCNPX neutronic analysis |
url | http://www.doiserbia.nb.rs/img/doi/1451-3994/2017/1451-39941704320M.pdf |
work_keys_str_mv | AT mirghaffarireza neutronicsimulationofacandu6reactorwithheavywaterbasednanofluidcoolant AT jahanfarniagholamreza neutronicsimulationofacandu6reactorwithheavywaterbasednanofluidcoolant AT athariallafmitra neutronicsimulationofacandu6reactorwithheavywaterbasednanofluidcoolant |