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

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.accessioned2025-04-10T11:10:15Z
dc.date.available2025-04-10T11:10:15Z
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.urihttp://hdl.handle.net/20.500.14701/49158
dc.publisherElsevier Ltd
dc.titleModification of the radial beam port of ITU TRIGA Mark II research reactor for BNCT applications
dc.typeArticle

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