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, IA
dc.contributor.authorÇolak, Ü
dc.contributor.authorOkka, M
dc.contributor.authorKiziltas, S
dc.date.accessioned2024-07-18T12:05:41Z
dc.date.available2024-07-18T12:05:41Z
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, thertnal/epithermal neutron flux, fast group photon fluence and change of the neutron fluxes with the beam port length are presented. (C) 2015 Elsevier Ltd. All rights reserved.
dc.identifier.issn0969-8043
dc.identifier.urihttp://akademikarsiv.cbu.edu.tr:4000/handle/123456789/9924
dc.language.isoEnglish
dc.publisherPERGAMON-ELSEVIER SCIENCE LTD
dc.subjectNEUTRON-CAPTURE THERAPY
dc.subjectEPITHERMAL-NEUTRON
dc.subjectIRRADIATION FACILITY
dc.subjectSPECTRA
dc.subjectHEU
dc.titleModification of the radial beam port of ITU TRIGA Mark II research reactor for BNCT applications
dc.typeArticle

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