Modification of the radial beam port of ITU TRIGA Mark II research reactor for BNCT applications
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Date
2015
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Abstract
This 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.
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Keywords
Boron Neutron Capture Therapy , Computer Simulation , Computer-Aided Design , Equipment Design , Equipment Failure Analysis , Models, Statistical , Monte Carlo Method , Nuclear Reactors , Scattering, Radiation , Activation analysis , Intelligent systems , Monte Carlo methods , Neutron flux , Research reactors , cadmium , gold , polyethylene , Beam ports , BNCT , Cerrobend , Istanbul Technical University , ITU TRIGA Mark II , Monte Carlo results , Photon fluence , Article , collimator , mathematical analysis , Monte Carlo method , neutron activation analysis , neutron capture therapy , neutron radiation , nuclear reactor , photon , priority journal , radiation beam , Turkey (republic) , computer aided design , computer simulation , device failure analysis , devices , equipment design , neutron capture therapy , nuclear reactor , radiation scattering , statistical model , Neutron activation analysis