### Abstract

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 language | English (US) |
---|---|

Pages (from-to) | 337-355 |

Number of pages | 19 |

Journal | Radiochimica Acta |

Volume | 89 |

Issue number | 4-5 |

State | Published - 2001 |

### Fingerprint

### Keywords

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

### ASJC Scopus subject areas

- Inorganic Chemistry
- Nuclear Energy and Engineering

### Cite this

*Radiochimica Acta*,

*89*(4-5), 337-355.

**A review of radiation dosimetry applications using the MCNP Monte Carlo code.** / Solberg, T. D.; DeMarco, J. J.; Chetty, I. J.; Mesa, A. V.; Cagnon, C. H.; Li, A. N.; Mather, K. K.; Medin, P. M.; Arellano, A. R.; Smathers, J. B.

Research output: Contribution to journal › Article

*Radiochimica Acta*, vol. 89, no. 4-5, pp. 337-355.

}

TY - JOUR

T1 - A review of radiation dosimetry applications using the MCNP Monte Carlo code

AU - Solberg, T. D.

AU - DeMarco, J. J.

AU - Chetty, I. J.

AU - Mesa, A. V.

AU - Cagnon, C. H.

AU - Li, A. N.

AU - Mather, K. K.

AU - Medin, P. M.

AU - Arellano, A. R.

AU - Smathers, J. B.

PY - 2001

Y1 - 2001

N2 - 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.

AB - 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.

KW - MCNP

KW - Medical physics

KW - Monte Carlo

KW - Radiation dosimetry

KW - Treatment planning

UR - http://www.scopus.com/inward/record.url?scp=0034967139&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=0034967139&partnerID=8YFLogxK

M3 - Article

AN - SCOPUS:0034967139

VL - 89

SP - 337

EP - 355

JO - Radiochimica Acta

JF - Radiochimica Acta

SN - 0033-8230

IS - 4-5

ER -