The Voxel Mice Model of MCNPX for Simulation In Vivo Test BNCT
Keywords:
voxel mice model, MCNPX, in vivo, BNCT
Abstract
A study of voxel mice model of MCNPX has been done for in vivo test Boron Neutron Capture Therapy (BNCT). Mathematical and parameters were used to construct the stylized Mice model phantom. The geometry was modified into simulation software MCNPX (Monte Carlo N-Particle eXtended) simulation input. The result of mice stylized model phantom has been showed Figure 3.Downloads
Download data is not yet available.
References
Li Y, Xia P, Wang X, Kong F, Huang Q: 2010. Start-up of the first in-hospital Neutron Irradiator (IHNI1) & presentation of the BNCT development status in China. Proc 14th Int’l Cong on Neutron Capture Therapy, New Challenges in Neutron Capture Therapy Oct 25–29; Buenos Aires, Argentina.
Huang, J. 2009. Boron Neutron Capture Therapy for Cancer Treatments
Burn K. W., C. Daffara, G. Gualdrini, M. Pierantoni, dan P. Ferrari. 2007.“Treating Voxel Geometries in Radiation Protection Dosimetry with A Patched Version of The Monte Carlo Codes MCNP and MCNPX.” Radiat Prot. Dosimetry, vol. 123, no. 3, pp. 345–53,
ICRP. 2009. “ICRP Publications 110: Adult Reference Computational Phantoms,”Annals of the ICRP, p.2,.
RSICC. 2008. MCNPX 2.6.0. Technical document, U.S. Department of Energy New Mexico,
C. Lee, C. Lee, D. Lodwick, dan W. E. Bolch. 2007. “NURBS-Based 3-D Anthropomorphic Computational Phantoms for Radiation Dosimetry Applications.” Radiat. Prot. Dosimetry, vol. 127, pp. 227–232,
International Atomic Energy Agency. 2011. Current Status of Neutron Capture Therapy, IAEA TECDOC-1223. Vienna: IAEA
X-5 Monte Carlo Team. 2003. MCNP – A General Monte Carlo N-Particle Transport Code, version 5. New Mexico: Los Alamos National Laboratory
Pinasti S.G. 2014. Reconstruction of Hybrid Computational Human Phantom For Internal Radiation Dosimetry Study In Radioiodine Therapy. Skripsi. Yogyakarta: Gadjah Mada University.
Konijnenberg, M.W., Bijster, M., Krenning E.P, de Jong M. 2015. A Stylized Computational Model of the Rat for Organ Dosimetry in Support of Preclinical Evaluations of Peptide Receptor Radionuclide Therapy with 90Y, 111In, or 177Lu. J Nucl Med 2004; 45:1260–1269
Achmad B. and Firdausy,K., 2013. Pengolahan Citra Digital Menggunakan Delphi. Andi Publishers, Yogyakarta,
Redd. R. A. 2003. Radiation Dosimetry and Medical Physics Calculations Using MCNP 5. Thesis, Nuclear Engineering Department, Texas A & M University, College Station,
Walker, S.J. 1998. Boron Neutron Capture Therapy: Principles and Prospects, Radiography , vol. 4, 1998, 211.
Huang, J. 2009. Boron Neutron Capture Therapy for Cancer Treatments
Burn K. W., C. Daffara, G. Gualdrini, M. Pierantoni, dan P. Ferrari. 2007.“Treating Voxel Geometries in Radiation Protection Dosimetry with A Patched Version of The Monte Carlo Codes MCNP and MCNPX.” Radiat Prot. Dosimetry, vol. 123, no. 3, pp. 345–53,
ICRP. 2009. “ICRP Publications 110: Adult Reference Computational Phantoms,”Annals of the ICRP, p.2,.
RSICC. 2008. MCNPX 2.6.0. Technical document, U.S. Department of Energy New Mexico,
C. Lee, C. Lee, D. Lodwick, dan W. E. Bolch. 2007. “NURBS-Based 3-D Anthropomorphic Computational Phantoms for Radiation Dosimetry Applications.” Radiat. Prot. Dosimetry, vol. 127, pp. 227–232,
International Atomic Energy Agency. 2011. Current Status of Neutron Capture Therapy, IAEA TECDOC-1223. Vienna: IAEA
X-5 Monte Carlo Team. 2003. MCNP – A General Monte Carlo N-Particle Transport Code, version 5. New Mexico: Los Alamos National Laboratory
Pinasti S.G. 2014. Reconstruction of Hybrid Computational Human Phantom For Internal Radiation Dosimetry Study In Radioiodine Therapy. Skripsi. Yogyakarta: Gadjah Mada University.
Konijnenberg, M.W., Bijster, M., Krenning E.P, de Jong M. 2015. A Stylized Computational Model of the Rat for Organ Dosimetry in Support of Preclinical Evaluations of Peptide Receptor Radionuclide Therapy with 90Y, 111In, or 177Lu. J Nucl Med 2004; 45:1260–1269
Achmad B. and Firdausy,K., 2013. Pengolahan Citra Digital Menggunakan Delphi. Andi Publishers, Yogyakarta,
Redd. R. A. 2003. Radiation Dosimetry and Medical Physics Calculations Using MCNP 5. Thesis, Nuclear Engineering Department, Texas A & M University, College Station,
Walker, S.J. 1998. Boron Neutron Capture Therapy: Principles and Prospects, Radiography , vol. 4, 1998, 211.
Published
2016-10-31
How to Cite
Prastowo, A., Sardjono, Y., & Widarto, W. (2016). The Voxel Mice Model of MCNPX for Simulation In Vivo Test BNCT. Indonesian Journal of Physics and Nuclear Applications, 1(3), 151-156. https://doi.org/10.24246/ijpna.v1i3.151-156
Issue
Section
Articles
This work is licensed under a Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International License.
Indonesian Journal of Physics and Nuclear Applications is licensed under a Creative Commons Attribution 4.0 International License.
