Neutronic Calculations for Certain Americium Mixed Fuels and Clads in a Boiling Water Reactor

Basit Öğe Kaydı
dc.contributor.authorDuz, Mehtap
dc.date.accessioned2024-08-04T20:49:25Z
dc.date.available2024-08-04T20:49:25Z
dc.date.issued2021
dc.departmentİnönü Üniversitesien_US
dc.description.abstractIn this study, a Boiling Water Reactor (BWR) design was made using the Monte Carlo (MCNPX) method. The reactor core in the designed BWR system was divided into an 8 x 8 square lattice with a constant pitch of 30.48 cm. In this study, americium (Am), which is found in the minor actinidine (MA) of spent nuclear fuel known as nuclear waste from existing reactors, was used as fuel with the addition of oxygen and fluorine. In this study, AmO2 and AmF3 fuels at the rate of 0.02-0.1 % were used as Americium Mixed Fuels, and Zircaloy-2 (Zr-2), SiC, and VC were used as clad. Neutronic calculations for certain Americium Mixed Fuels and clads were compared in the designed BWR system. In the BWR system designed in the study; k(eff) , neutron flux, fission energy, heating, and depleted Am were calculated. The three-dimensional (3-D) modeling of the designed BWR system was performed by using MCNPX-2.7.0 Monte Carlo method and the ENDF/B-VII.0 nuclear data library.en_US
dc.description.sponsorshipInonu University Scientific Research Projects Unit [FBA-2020-2307]en_US
dc.description.sponsorshipThis work was supported by Inonu University Scientific Research Projects Unit with the project number FBA-2020-2307.en_US
dc.identifier.doi10.3389/fenrg.2021.639416
dc.identifier.issn2296-598X
dc.identifier.scopus2-s2.0-85103055609en_US
dc.identifier.scopusqualityQ2en_US
dc.identifier.urihttps://doi.org/10.3389/fenrg.2021.639416
dc.identifier.urihttps://hdl.handle.net/11616/99849
dc.identifier.volume9en_US
dc.identifier.wosWOS:000630535400001en_US
dc.identifier.wosqualityQ3en_US
dc.indekslendigikaynakWeb of Scienceen_US
dc.indekslendigikaynakScopusen_US
dc.language.isoenen_US
dc.publisherFrontiers Media Saen_US
dc.relation.ispartofFrontiers in Energy Researchen_US
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/openAccessen_US
dc.subjectboiling water reactoren_US
dc.subjectkeffen_US
dc.subjectneutron fluxen_US
dc.subjectfission energyen_US
dc.subjectheatingen_US
dc.subjectMCNPX-2.7.0en_US
dc.titleNeutronic Calculations for Certain Americium Mixed Fuels and Clads in a Boiling Water Reactoren_US
dc.typeArticleen_US

Dosyalar

Koleksiyon

WoS İndeksli Yayınlar Koleksiyonu
Scopus İndeksli Yayınlar Koleksiyonu