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Utilization of thorium and U-ZrH1.6 fuels in various heterogeneous cores for TRIGA PUSPATI Reactor (RTP)

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dc.contributor.authorBin Damahuri A.H.en_US
dc.contributor.authorMohamed H.en_US
dc.contributor.authorMohamed A.A.en_US
dc.contributor.authorIdris F.en_US
dc.contributor.authorid57201214590en_US
dc.contributor.authorid57136356100en_US
dc.contributor.authorid57190936088en_US
dc.contributor.authorid6701397678en_US
dc.date.accessioned2023-05-29T06:53:04Z
dc.date.available2023-05-29T06:53:04Z
dc.date.issued2018
dc.descriptionFuels; Nuclear fuels; Ore treatment; Ores; Thoria; Thorium; Uranium; Uranium compounds; Core configuration; Effective multiplication factor; Heterogeneous cores; Malaysian governments; Mineral processing; Monte carlo n particles; Research and development; Thorium extraction; Zirconium compoundsen_US
dc.description.abstractThe use of thorium as nuclear fuel has been an appealing prospect for many years and will be great significance to nuclear power generation. There is an increasing need for more research on thorium as Malaysian government is currently active in the national Thorium Flagship Project, which was launched in 2014. The thorium project, which is still in phase 1, focuses on the research and development of the thorium extraction from mineral processing ore. Thus, the aim of the study is to investigate other alternative TRIGA PUSPATI Reactor (RTP) core designs that can fully utilize thorium. Currently, the RTP reactor has an average neutron flux of 2.797 x 1012 cm-2/s-1 and an effective multiplication factor, k eff, of 1.001. The RTP core has a circular array core configuration with six circular rings. Each ring consists of 6, 12, 18, 24, 30 or 36 U-ZrH1.6 fuel rods. There are three main type of uranium weight, namely 8.5, 12 and 20 wt.%. For this research, uranium zirconium hydride (U-ZrH1.6) fuel rods in the RTP core were replaced by thorium (ThO2) fuel rods. Seven core configurations with different thorium fuel rods placements were modelled in a 2D structure and simulated using Monte Carlo n-particle (MCNPX) code. Results show that the highest initial criticality obtained is around 1.35101. Additionally there is a significant discrepancy between results from previous study and the work because of the large estimated leakage probability of approximately 21.7% and 2D model simplification. � Published under licence by IOP Publishing Ltd.en_US
dc.description.natureFinalen_US
dc.identifier.ArtNo12034
dc.identifier.doi10.1088/1757-899X/298/1/012034
dc.identifier.issue1
dc.identifier.scopus2-s2.0-85043977310
dc.identifier.urihttps://www.scopus.com/inward/record.uri?eid=2-s2.0-85043977310&doi=10.1088%2f1757-899X%2f298%2f1%2f012034&partnerID=40&md5=268a26a4da8fc804cea35cbd21746d7a
dc.identifier.urihttps://irepository.uniten.edu.my/handle/123456789/23909
dc.identifier.volume298
dc.publisherInstitute of Physics Publishingen_US
dc.relation.ispartofAll Open Access, Bronze
dc.sourceScopus
dc.sourcetitleIOP Conference Series: Materials Science and Engineering
dc.titleUtilization of thorium and U-ZrH1.6 fuels in various heterogeneous cores for TRIGA PUSPATI Reactor (RTP)en_US
dc.typeConference Paperen_US
dspace.entity.typePublication
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