Three Dose Calculation Codes Applied to Neutron Transport in BNCT
The three dimensional BNCT_Rtpe/rtt.MC1 is used for treatment planning in the proposed patient irradiations at the Finnish boron neutron capture therapy (BNCT) facility FiR 1. Two other radiation transport calculation codes used mainly in the characterization of the treatment beam, are DORT (Two-Dimensional Discrete Ordinates Transport Code)2 and MCNP (Monte Carlo N-Particle Transport Code System).3
KeywordsBoron Neutron Capture Therapy Thermal Neutron Flux Transport Code Neutron Transport Flux Gradient
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