Journal of Nuclear Science, Engineering and Technology (JONSAT)
In cooperation with the Iranian Nuclear Society

Calculation of Dose Distribution in Neutron Brachytherapy Using 252-Cf Source Through the Monte Carlo Simulation and Comparison with Experimental Data

Document Type : Research Paper

Authors

Gh Izadi Vasafi 1
M. M Firoozabadi 1
I Jabari 2

1 Department of Physics, University of Birjand Birjand - Iran

2 Department of Nuclear Engineering, Esfahan University-Esfahan – Iran

https://doi.org/10.24200/nst.2018.188
Abstract
Detailed recognition of dose distribution around the brachytherapy sources in order to create appropriate plans for treatment of cancer is very important. In this study, with calculation of the dosimetric parameters of clinical 252Cf source based on TG-43U1 protocol and utilizing different tallies of dose calculation in MCNPX code [F4 (Fluence Tally), F6 (Kerma Tally) and *F8 (Dose Tally)], the dose rate at different directions and distances from the source center has been determined and compared with other experimental and simulation results. By comparing the results of this study with the experimental measurements and observing the good adaptation of the results, it was observed that the dose rate of clinical 252Cf source has its largest value at the direction of longitudinal axis of the source, which is the reason for more expansion of radioactive material distribution in this direction, in comparsion with other directions and consequently higher neutron flux in this direction, based on the angular dependance of dose rate to geometric function according to TG-43 protocol. It was also found that the F4 and F6 tally results in neutron dosimetry calculations are more accurate than the *F8 tally results. The dosimetry calculations performed in this study has provided a preliminary dosimetry characterization of 252Cf neutron sources for usage in treatment plans in the country.

Highlights

[1] C.S. Shlea, D.H. Stoddard, Californium isotopes proposed for intracavity and interstitial radiation therapy with neutrons, Nature, 206 (1965) 1058-1059.

 [2] L.L. Anderson, Status of dosimetry for 252Cf medical neutron sources, Phys. Med, 18 (1973) 779-799.

 [3] J.G. Wierzbicki, M.J. Rivard, W. Roberts, Physics and dosimetry of clinical 252Cf sources, Kluwer Academic, 29 (1997) 25-53.

 [4] R.C. Martin, R.R. Laxson, J.H. Miller, J.G. Wierzbicki, M.J. Rivard, D.L. Marsh, Development of high-activity 252Cf sources for neutron brachytherapy, Appl. Radiat. Isot, 48 (1997) 1567-1570.

 [5] J. Ghassoun, D. Mostacci, V. Molinari, A.J. ehouani, Detailed dose distribution prediction of Cf-252 brachytherapy source with boron loading dose enhancement, Applied Radiation and Isotopes, 68 (2010) 265-270.

 [6] M.J. Rivard, Neutron dosimetry for a general 252Cf brachytherapy source, Medical Physics, 27  (2000) 2803-2815.

 [7] L. Paredes, J. Azorin, M. Balcazar, J.L. Francois, Neutrons absorbed dose rate calculations for interstitial brachytherapy with 252Cf sources, Nuclear Instruments and Methods in Physics Research A, 580 (2007) 582–585.

 [8] R. Nath, L.L. Anderson, G. Luxton, K.A. Weaver, J.F. Williamson, A.S. Meigooni, Dosimetry of interstitial brachytherapy sources: Recommendations of the AAPM Radiation Therapy Committee Task Group, No. 43, Med. Phys, 22 (1995) 209-234.

 [9] M.J. Rivard, J.G. Wierzbicki, F. Van den Heuvel, R.C. Martin, R.R. McMahon, Clinical brachytherapy with neutron emitting 252Cf sources and adherence to AAPM TG-43 dosimetry protocol, Med. Phys, 26 (1999) 87–96.

  [10] M.J. Rivard, B.M. Coursey, L.A. Dewerd, W.F. Hanson, M. Saiful Huq, G.S. Ibbott, Update of AAPM Task Group Report No. 43: A revised AAPM protocol for brachytherapy dose calculations, Med Phys, 31 (2004) 633-674.

 [11] M.J. Rivard, J.K. Sganga, F. Errico, J.S. Tsai, K. Ulin, M.J. Engler, Calculated neutron air kerma strength conversion factors for a generically encapsulated Cf-252 brachytherapy source, Nuclear Instruments and Methods in Physics Research A, 476 (2002) 119–122.

 [12] G. Raisali, F. Mokhles Gerami, R. Khodadadi, B. Piroozfar, Determination of Dosimetery Parameters for Low Energy Brachytherapy Sources Based on TG-43U1 Protocol Using Different MCNP Tallies, Journal of Nuclear Science and Technology, 35 (1384) 29-36. 

 [13] LS. (Ed.)Walter, LANL(Los Alamos National Laboratory) Monte Carlo N-Particle transport code system for multiparticle and high energy applications. Version 270, LA-CP-02-408, Los Alamos National  Laboratory (2002).

 [14] M.B. Chadwick, H.H. Barschall, R.S. Caswell, A consistent set of neutron kerma coefficients from  thermal to 150MeV for biologically important materials, Med. Phys, 26 (1999) 974-991.

 [15] R.D. Colvett, H.H. Rossi, V. Krishnaswamy, Dose distributions around a californium-252 needle,  Phys. Med. Biol, 17 (1972) 356-364.

 [16] J.C. Yanch, R.G. Zamenhof, Dosimetry of 252Cf source for neutron radio therapy with and without augmentation of boron neutron capture therapy. Radiat. Res, 131 (1992) 249–256.

Keywords

Brachytherapy
Neutron
252Cf
Dosimetry
MCNP
[1] C.S. Shlea, D.H. Stoddard, Californium isotopes proposed for intracavity and interstitial radiation therapy with neutrons, Nature, 206 (1965) 1058-1059.
 [2] L.L. Anderson, Status of dosimetry for 252Cf medical neutron sources, Phys. Med, 18 (1973) 779-799.
 [3] J.G. Wierzbicki, M.J. Rivard, W. Roberts, Physics and dosimetry of clinical 252Cf sources, Kluwer Academic, 29 (1997) 25-53.
 [4] R.C. Martin, R.R. Laxson, J.H. Miller, J.G. Wierzbicki, M.J. Rivard, D.L. Marsh, Development of high-activity 252Cf sources for neutron brachytherapy, Appl. Radiat. Isot, 48 (1997) 1567-1570.
 [5] J. Ghassoun, D. Mostacci, V. Molinari, A.J. ehouani, Detailed dose distribution prediction of Cf-252 brachytherapy source with boron loading dose enhancement, Applied Radiation and Isotopes, 68 (2010) 265-270.
 [6] M.J. Rivard, Neutron dosimetry for a general 252Cf brachytherapy source, Medical Physics, 27  (2000) 2803-2815.
 [7] L. Paredes, J. Azorin, M. Balcazar, J.L. Francois, Neutrons absorbed dose rate calculations for interstitial brachytherapy with 252Cf sources, Nuclear Instruments and Methods in Physics Research A, 580 (2007) 582–585.
 [8] R. Nath, L.L. Anderson, G. Luxton, K.A. Weaver, J.F. Williamson, A.S. Meigooni, Dosimetry of interstitial brachytherapy sources: Recommendations of the AAPM Radiation Therapy Committee Task Group, No. 43, Med. Phys, 22 (1995) 209-234.
 [9] M.J. Rivard, J.G. Wierzbicki, F. Van den Heuvel, R.C. Martin, R.R. McMahon, Clinical brachytherapy with neutron emitting 252Cf sources and adherence to AAPM TG-43 dosimetry protocol, Med. Phys, 26 (1999) 87–96.
  [10] M.J. Rivard, B.M. Coursey, L.A. Dewerd, W.F. Hanson, M. Saiful Huq, G.S. Ibbott, Update of AAPM Task Group Report No. 43: A revised AAPM protocol for brachytherapy dose calculations, Med Phys, 31 (2004) 633-674.
 [11] M.J. Rivard, J.K. Sganga, F. Errico, J.S. Tsai, K. Ulin, M.J. Engler, Calculated neutron air kerma strength conversion factors for a generically encapsulated Cf-252 brachytherapy source, Nuclear Instruments and Methods in Physics Research A, 476 (2002) 119–122.
 [12] G. Raisali, F. Mokhles Gerami, R. Khodadadi, B. Piroozfar, Determination of Dosimetery Parameters for Low Energy Brachytherapy Sources Based on TG-43U1 Protocol Using Different MCNP Tallies, Journal of Nuclear Science and Technology, 35 (1384) 29-36. 
 [13] LS. (Ed.)Walter, LANL(Los Alamos National Laboratory) Monte Carlo N-Particle transport code system for multiparticle and high energy applications. Version 270, LA-CP-02-408, Los Alamos National  Laboratory (2002).
 [14] M.B. Chadwick, H.H. Barschall, R.S. Caswell, A consistent set of neutron kerma coefficients from  thermal to 150MeV for biologically important materials, Med. Phys, 26 (1999) 974-991.
 [15] R.D. Colvett, H.H. Rossi, V. Krishnaswamy, Dose distributions around a californium-252 needle,  Phys. Med. Biol, 17 (1972) 356-364.
 [16] J.C. Yanch, R.G. Zamenhof, Dosimetry of 252Cf source for neutron radio therapy with and without augmentation of boron neutron capture therapy. Radiat. Res, 131 (1992) 249–256.

Home