Measurement of in-phantom neutron flux and gamma dose in Tehran research reactor boron neutron capture therapy beam line

Aim: Determination of in-phantom quality factors of Tehran research reactor (TRR) boron neutron capture therapy (BNCT) beam. Materials and Methods: The doses from thermal neutron reactions with N-14 and B-10 are calculated by kinetic energy released per unit mass approach, after measuring thermal neutron flux using neutron activation technique. Gamma dose is measured using TLD-700 dosimeter. Results: Different dose components have been measured in a head phantom which has been designed and constructed for BNCT purpose in TRR. Different in-phantom beam quality factors have also been determined. Conclusions: This study demonstrates that the TRR BNCT beam line has potential for treatment of superficial tumors.