Modification of the radial beam port of ITU TRIGA Mark II research reactor for BNCT applications.
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.
Department of Biophysics, School of Medicine, Celal Bayar University, Manisa, Turkey.
Zafer
Z
Akan
Department of Nuclear Engineering, Hacettepe University, Beytepe Campus, Ankara, Turkey. Electronic address: tm@hacettepe.edu.tr.
Mehmet
M
Türkmen
Department of Radiation Oncology, School of Medicine, Yüzüncü Yıl University, Van, Turkey.
Tahir
T
Çakir
Energy Institute, Istanbul Technical University, Ayazağa Campus, Maslak, Sarıyer, İstanbul, Turkey.
İskender A
İA
Reyhancan
Energy Institute, Istanbul Technical University, Ayazağa Campus, Maslak, Sarıyer, İstanbul, Turkey.
Üner
Ü
Çolak
Energy Institute, Istanbul Technical University, Ayazağa Campus, Maslak, Sarıyer, İstanbul, Turkey.
Muhittin
M
Okka
Energy Institute, Istanbul Technical University, Ayazağa Campus, Maslak, Sarıyer, İstanbul, Turkey.
Sahip
S
Kiziltaş
D016754:Boron Neutron Capture Therapy / Q000295:instrumentation*; D003198:Computer Simulation; D017076:Computer-Aided Design; D004867:Equipment Design; D019544:Equipment Failure Analysis; D015233:Models, Statistical; D009010:Monte Carlo Method; D009688:Nuclear Reactors / Q000295:instrumentation*; D012542:Scattering, Radiation
BNCT; ITU TRIGA Mark II; Monte-Carlo simulation; PE and Cerrobend collimator; Radial beam port