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

Zafer Akan; Mehmet Türkmen; Tahir Çakir; İskender A Reyhancan; Üner Çolak; Muhittin Okka; Sahip Kiziltaş

doi:10.1016/j.apradiso.2015.02.014

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

Appl Radiat Isot. 2015 May:99:110-6. doi: 10.1016/j.apradiso.2015.02.014. Epub 2015 Feb 23.

Authors

Zafer Akan¹, Mehmet Türkmen², Tahir Çakir³, İskender A Reyhancan⁴, Üner Çolak⁴, Muhittin Okka⁴, Sahip Kiziltaş⁴

Affiliations

¹ Department of Biophysics, School of Medicine, Celal Bayar University, Manisa, Turkey.
² Department of Nuclear Engineering, Hacettepe University, Beytepe Campus, Ankara, Turkey. Electronic address: tm@hacettepe.edu.tr.
³ Department of Radiation Oncology, School of Medicine, Yüzüncü Yıl University, Van, Turkey.
⁴ Energy Institute, Istanbul Technical University, Ayazağa Campus, Maslak, Sarıyer, İstanbul, Turkey.

PMID: 25746919
DOI: 10.1016/j.apradiso.2015.02.014

Abstract

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.

Keywords: BNCT; ITU TRIGA Mark II; Monte-Carlo simulation; PE and Cerrobend collimator; Radial beam port.

Publication types

Research Support, Non-U.S. Gov't

MeSH terms

Boron Neutron Capture Therapy / instrumentation*
Computer Simulation
Computer-Aided Design
Equipment Design
Equipment Failure Analysis
Models, Statistical*
Monte Carlo Method
Nuclear Reactors / instrumentation*
Scattering, Radiation