A review of radiation dosimetry applications using the MCNP Monte Carlo code

T. D. Solberg, J. J. DeMarco, I. J. Chetty, A. V. Mesa, C. H. Cagnon, A. N. Li, K. K. Mather, P. M. Medin, A. R. Arellano, J. B. Smathers

Research output: Contribution to journalArticlepeer-review

35 Scopus citations


The Monte Carlo code MCNP (Monte Carlo N-Particle) has a significant history dating to the early years of the Manhattan Project. More recently, MCNP has been used successfully to solve many problems in the field of medical physics. In radiotherapy applications MCNP has been used successfully to calculate the bremsstrahlung spectra from medical linear accelerators, for modeling the dose distributions around high dose rate brachytherapy sources, and for evaluating the dosimetric properties of new radioactive sources used in intravascular irradiation for prevention of restenosis following angioplasty. MCNP has also been used for radioimmunotherapy and boron neutron capture therapy applications. It has been used to predict fast neutron activation of shielding and biological materials. One area that holds tremendous clinical promise is that of radiotherapy treatment planning. In diagnostic applications, MCNP has been used to model X-ray computed tomography and position emission tomography scanners, to compute the dose delivered from CT procedures, and to determine detector characteristics of nuclear medicine devices. MCNP has been used to determine particle fluxes around radiotheraphy treatment devices and to perform shielding calculations in radiotherapy treatment rooms. This manuscript is intended to provide to the reader a comprehensive summary of medical physics applications of the MCNP code.

Original languageEnglish (US)
Pages (from-to)337-355
Number of pages19
JournalRadiochimica Acta
Issue number4-5
StatePublished - 2001


  • MCNP
  • Medical physics
  • Monte Carlo
  • Radiation dosimetry
  • Treatment planning

ASJC Scopus subject areas

  • Physical and Theoretical Chemistry


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