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Three Dose Calculation Codes Applied to Neutron Transport in BNCT

  • Juha S. Lampinen
  • Tiina Seppälä
  • Iiro Auterinen
  • Sauli Savolainen

Abstract

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

Keywords

Boron Neutron Capture Therapy Thermal Neutron Flux Transport Code Neutron Transport Flux Gradient 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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References

  1. 1.
    D.E. Wessol, et al., http://id.inel.gov/cartlrtpe-manual.Google Scholar
  2. 2.
    W.A. Rhoades, and R.L. Childs, The DORT Two-Dimensional Discrete Ordinates Transport Code, Nucl. Sci & Eng, 99:88–89, 1988.Google Scholar
  3. 3.
    J.F. Briesmeister ed., “MCNP-A General Monte Carlo N-Particle Transport Code”, Los Alamos National Laboratory Report, LA-12625-M 1997.Google Scholar
  4. 4.
    T. Seppälä, T. Serén, and I. Auterinen, Source characterisation for the rtt_MC treatment planning program at FiR1, these proceedings (submitted).Google Scholar

Copyright information

© Springer Science+Business Media New York 2001

Authors and Affiliations

  • Juha S. Lampinen
    • 1
    • 2
  • Tiina Seppälä
    • 1
    • 3
  • Iiro Auterinen
    • 4
  • Sauli Savolainen
    • 2
  1. 1.Department of PhysicsUniversity of HelsinkiFinland
  2. 2.Department of RadiologyUSA
  3. 3.Clinical Research InstituteHelsinki University Central HospitalFinland
  4. 4.VTT Chemical TechnologyEspooFinland

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