The Voxel Mice Model of MCNPX for Simulation In Vivo Test BNCT

Authors

  • Agung Prastowo Sebelas Maret University
  • Yohannes Sardjono Center of Science and Technology of Accelerator; National Nuclear Energy Agency
  • Widarto Widarto Center of Science and Technology of Accelerator; National Nuclear Energy Agency

DOI:

https://doi.org/10.24246/ijpna.v1i3.151-156

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.

Downloads

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

Vol. 1 No. 3 (2016)

Section

Articles

License

Creative Commons License
Indonesian Journal of Physics and Nuclear Applications is licensed under a Creative Commons Attribution 4.0 International License.