Chinese Physics C > 2003, Vol. 27 > Issue(10): 936-942

Monte Carlo Simulation of Boron Neutron Capture Therapy

Graduate School of China Academe of Engineer Physics,Beijing 100088.China2 Lab.Com.Phy.,Institute of Applied Physics and Computational Mathematics,Beijing 100088,China

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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.

References

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Marashi M K. Nuclear instrumem and Methods in Physics Research, 2000, A 440: 446–452 2 Rorer D, Wambersie A, Whitmore G. et al. edited, Current Status of neutron capture therapy, IAEA, 20013 Briesmeister J F. MCNP–A General Monte Carlo Code for N–Particle Transport Code, LA–12625–M(March, 1997)4 Goorley J T, Kiger W S, Ⅲ, Zamenhof R G. Medical Physics, 2002, 29: 145–1565 ICRU63, International Commission on Radiation Units and Measurements, 2000, Bethesda, MD

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QIU You-Heng, DENG Li, YING Yang-Jun and XIAO Gang. Monte Carlo Simulation of Boron Neutron Capture Therapy[J]. Chinese Physics C, 2003, 27(10): 936-942.

QIU You-Heng, DENG Li, YING Yang-Jun and XIAO Gang. Monte Carlo Simulation of Boron Neutron Capture Therapy[J]. Chinese Physics C, 2003, 27(10): 936-942. shu

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Received: 2003-01-28
Revised: 1900-01-01

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沈阳化工大学材料科学与工程学院沈阳 110142

Monte Carlo Simulation of Boron Neutron Capture Therapy

Corresponding author:QIU You-Heng,

Graduate School of China Academe of Engineer Physics,Beijing 100088.China2 Lab.Com.Phy.,Institute of Applied Physics and Computational Mathematics,Beijing 100088,China

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 from¹⁰B(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.