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

• Using MCNP5, radial beam port of ITU TRIGA Mark II research reactor is modified.
• Polyethylene and Cerrobend collimators are used to modify the beam port.
• Results of two-group neutron/photon flux are presented.
• Monte Carlo results are compared with experimental results.

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.