Design of a filtration system to improve the dose distribution of an accelerator‐based neutron capture therapy system

PURPOSE: The aim of this study is to design and evaluate a neutron filtration system to improve the dose distribution of an accelerator‐based neutron capture therapy system. METHODS: An LiF‐sintered plate composed of 99%‐enriched (6)Li was utilized to filter out low‐energy neutrons to increase the average neutron energy at the beam exit. A 5‐mm thick filter to fit inside a 12‐cm diameter circular collimator was manufactured, and experimental measurements were performed to measure the thermal neutron flux and gamma‐ray dose rate inside a water phantom. The experimental measurements were compared with the Monte Carlo simulation, particle, and heavy ion transport code system. Following the experimental verification, three filter designs were modeled, and the thermal neutron flux and the biologically weighted dose distribution inside a phantom were simulated. Following the phantom simulation, a dummy patient CT dataset was used to simulate a boron neutron capture therapy (BNCT) irradiation of the brain. A mock tumor located at 4, 6, 8 cm along the central axis and 4‐cm off‐axis was set, and the dose distribution was simulated for a maximum total biologically weighted brain dose of 12.5 Gy with a beam entering from the vertex. RESULTS: All three filters improved the beam penetration of the accelerator‐based neutron source. Filter design C was found to be the most suitable filter, increasing the advantage depth from 9.1 to 9.9 cm. Compared with the unfiltered beam, the mean weighted dose in the tumor located at a depth of 8 cm along the beam axis was increased by ∼25%, and 34% for the tumor located at a depth of 8 cm and off‐axis by 4 cm. CONCLUSION: A neutron filtration system for an accelerator‐based BNCT system was investigated using Monte Carlo simulation. The proposed filter design significantly improved the dose distribution for the treatment of deep targets in the brain.