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

摘要

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 14N and 10B 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.