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The purpose of this study is to test the applicability of k 0 -INAA method at the Istanbul Technical University TRIGA Mark II research reactor. The neutron spectrum parameters such as epithermal neutron flux distribution parameter ( α ), thermal to epithermal neutron flux ratio ( f ) and thermal neutron flux ( φ th ) were determined at the central irradiation channel of the ITU TRIGA Mark II research reactor using bare triple-monitor method. HPGe detector calibrations and calculations were carried out by k 0 -IAEA software. The α , f and φ th values were calculated to be −0.009, 15.4 and 7.92·10 12 cm −2 s −1 , respectively. NIST SRM 1633b coal fly ash and intercomparison samples consisting of clay and sandy soil samples were used to evaluate the validity of the method. For selected elements, the statistical evaluation of the analysis results was carried out by z -score test. A good agreement between certified/reported and experimental values was obtained. [ABSTRACT FROM AUTHOR]

This paper aims to describe the modification of the radial beam port of ITU (İstanbul 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. [ABSTRACT FROM AUTHOR]