The Effect on Neutronic Calculations of Certain Alternative Fuels in a Boiling Water Reactor by Using MCNPX Monte Carlo Method

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dc.authorwosidDÜZ, Mehtap/AAS-3672-2020
dc.contributor.authorGunay, M.
dc.contributor.authorEspinoza, V. H. Sanchez
dc.contributor.authorTravleev, A.
dc.date.accessioned2024-08-04T20:41:19Z
dc.date.available2024-08-04T20:41:19Z
dc.date.issued2015
dc.departmentİnönü Üniversitesien_US
dc.descriptionInternational Conference on Computational and Experimental Science and Engineering (ICCESEN) -- OCT 25-29, 2014 -- Antalya, TURKEYen_US
dc.description.abstractWe were studying on the modeling of boiling water reactor fuel assemblies at pin-by-pin level by using Monte Carlo method. The designed boiling water reactor system is cylinder, and the radius of the cylinder is 228 cm. The total active core height is 315.79 cm. The reactor core was divided into the square lattice 7 x 7 type with a constant pitch of 30 cm. The core was surrounded with the reflector. The reflector was surrounded by SS316LN ferritic steel with width of 3 cm. The mixtures 0.21-% PuF4 and PuO2 were used as fuel. In this study, the effect on the neutronic calculations of PuF4 and PuO2 fuels was investigated in the designed boiling water reactor system. There were calculated k(eff), heat deposition and the fission energy in the designed boiling water reactor system. The three-dimensional (3D) modelling of the reactor core and fuel assembly into the designed boiling water reactor system was performed by using MCNPX-2.7.0 Monte Carlo method and the ENDF/B nuclear data library.en_US
dc.identifier.doi10.12693/APhysPolA.128.B-110
dc.identifier.endpageB112en_US
dc.identifier.issn0587-4246
dc.identifier.issn1898-794X
dc.identifier.issue2Ben_US
dc.identifier.scopus2-s2.0-84947782454en_US
dc.identifier.scopusqualityQ4en_US
dc.identifier.startpageB110en_US
dc.identifier.urihttps://doi.org/10.12693/APhysPolA.128.B-110
dc.identifier.urihttps://hdl.handle.net/11616/97061
dc.identifier.volume128en_US
dc.identifier.wosWOS:000363011700030en_US
dc.identifier.wosqualityQ4en_US
dc.indekslendigikaynakWeb of Scienceen_US
dc.indekslendigikaynakScopusen_US
dc.language.isoenen_US
dc.publisherPolish Acad Sciences Inst Physicsen_US
dc.relation.ispartofActa Physica Polonica Aen_US
dc.relation.publicationcategoryKonferans Öğesi - Uluslararası - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/openAccessen_US
dc.subjectCross-Sectionsen_US
dc.titleThe Effect on Neutronic Calculations of Certain Alternative Fuels in a Boiling Water Reactor by Using MCNPX Monte Carlo Methoden_US
dc.typeConference Objecten_US

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