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

Akan Z.Türkmen M.Çakir T.Reyhancan T.A.Çolak T.Okka M.Kiziltaş S.2024-07-222024-07-22201509698043http://akademikarsiv.cbu.edu.tr:4000/handle/123456789/16333This 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.EnglishBoron Neutron Capture TherapyComputer SimulationComputer-Aided DesignEquipment DesignEquipment Failure AnalysisModels, StatisticalMonte Carlo MethodNuclear ReactorsScattering, RadiationActivation analysisIntelligent systemsMonte Carlo methodsNeutron fluxResearch reactorscadmiumgoldpolyethyleneBeam portsBNCTCerrobendIstanbul Technical UniversityITU TRIGA Mark IIMonte Carlo resultsPhoton fluenceArticlecollimatormathematical analysisMonte Carlo methodneutron activation analysisneutron capture therapyneutron radiationnuclear reactorphotonpriority journalradiation beamTurkey (republic)computer aided designcomputer simulationdevice failure analysisdevicesequipment designneutron capture therapynuclear reactorradiation scatteringstatistical modelNeutron activation analysisModification of the radial beam port of ITU TRIGA Mark II research reactor for BNCT applicationsArticle10.1016/j.apradiso.2015.02.014