Modification of the radial beam port of ITU TRIGA Mark II research reactor for BNCT applications

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dc.contributor.authorAkan Z.
dc.contributor.authorTürkmen M.
dc.contributor.authorÇakir T.
dc.contributor.authorReyhancan T.A.
dc.contributor.authorÇolak T.
dc.contributor.authorOkka M.
dc.contributor.authorKiziltaş S.
dc.date.accessioned2024-07-22T08:13:24Z
dc.date.available2024-07-22T08:13:24Z
dc.date.issued2015
dc.description.abstractThis paper aims to describe the modification of the radial beam port of ITU (Istanbul Technical University) TRIGA Mark II research reactor for BNCT applications. Radial beam port is modified with Polyethylene and Cerrobend collimators. Neutron flux values are measured by neutron activation analysis (Au-Cd foils). Experimental results are verified with Monte Carlo results. The results of neutron/photon spectrum, thermal/epithermal neutron flux, fast group photon fluence and change of the neutron fluxes with the beam port length are presented. © 2015 Elsevier Ltd.
dc.identifier.DOI-ID10.1016/j.apradiso.2015.02.014
dc.identifier.issn09698043
dc.identifier.urihttp://akademikarsiv.cbu.edu.tr:4000/handle/123456789/16333
dc.language.isoEnglish
dc.publisherElsevier Ltd
dc.subjectBoron Neutron Capture Therapy
dc.subjectComputer Simulation
dc.subjectComputer-Aided Design
dc.subjectEquipment Design
dc.subjectEquipment Failure Analysis
dc.subjectModels, Statistical
dc.subjectMonte Carlo Method
dc.subjectNuclear Reactors
dc.subjectScattering, Radiation
dc.subjectActivation analysis
dc.subjectIntelligent systems
dc.subjectMonte Carlo methods
dc.subjectNeutron flux
dc.subjectResearch reactors
dc.subjectcadmium
dc.subjectgold
dc.subjectpolyethylene
dc.subjectBeam ports
dc.subjectBNCT
dc.subjectCerrobend
dc.subjectIstanbul Technical University
dc.subjectITU TRIGA Mark II
dc.subjectMonte Carlo results
dc.subjectPhoton fluence
dc.subjectArticle
dc.subjectcollimator
dc.subjectmathematical analysis
dc.subjectMonte Carlo method
dc.subjectneutron activation analysis
dc.subjectneutron capture therapy
dc.subjectneutron radiation
dc.subjectnuclear reactor
dc.subjectphoton
dc.subjectpriority journal
dc.subjectradiation beam
dc.subjectTurkey (republic)
dc.subjectcomputer aided design
dc.subjectcomputer simulation
dc.subjectdevice failure analysis
dc.subjectdevices
dc.subjectequipment design
dc.subjectneutron capture therapy
dc.subjectnuclear reactor
dc.subjectradiation scattering
dc.subjectstatistical model
dc.subjectNeutron activation analysis
dc.titleModification of the radial beam port of ITU TRIGA Mark II research reactor for BNCT applications
dc.typeArticle

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