Radiation shielding design of BNCT treatment room for D-T neutron source.
Recent studies have shown that D-T neutron generator can be used as a proper neutron source for Boron Neutron Capture Therapy (BNCT) of deep-seated brain tumors. In this paper, radiation shielding calculations have been conducted based on the computational method for designing a BNCT treatment room for a recent proposed D-T neutron source. By using the MCNP-4C code, the geometry of the treatment room has been designed and optimized in such a way that the equivalent dose rate out of the treatment room to be less than 0.5μSv/h for uncontrolled areas. The treatment room contains walls, monitoring window, maze and entrance door. According to the radiation protection viewpoint, dose rate results of out of the proposed room showed that using D-T neutron source for BNCT is safe.
Department of Physics, K.N. Toosi University of Technology, P.O. Box 15875-4416, Tehran, Iran.
Mehdi
M
Pouryavi
Department of Physics, K.N. Toosi University of Technology, P.O. Box 15875-4416, Tehran, Iran. Electronic address: masoudi@kntu.ac.ir.
S
S
Farhad Masoudi
Department of Physics, K.N. Toosi University of Technology, P.O. Box 15875-4416, Tehran, Iran.
Faezeh
F
Rahmani
BNCT; D-T neutron source; Equivalent dose rate; MCNP-4C; Treatment room