Monte Carlo Simulation of Boron Neutron Capture Therapy
- Received Date: 2003-01-28
- Accepted Date: 1900-01-01
- Available Online: 2003-10-05
Abstract: This paper introduces the particle transport process in brain, which is simulated by general Monte Carlo code MCNP. The absorbed dose rates from 10B(n,a)7Li,14N(n,p)14C,1H(n,r)2D and fast neutron elastic scattering reaction are considered. The major contribution to the tumor zone is from the neutron capture reaction of boron. The comparison of the absorbed dose rates from thermal and epithermal neutron indicates that the epithermal neutron beam is more effective than thermal neutron beam in destroying deep-seated tumors,on the contrary,the latter is valid for shallow tumor,e.g.skin cancer.In comparison with deterministic method DOSE program, MCNP code is convenient in simulation of Boron Neutron Capture Therapy.