The Optimization of Collimator Material and In Vivo Testing Dosimetry of Boron Neutron Capture Therapy (BNCT) on Radial Piercing Beam Port Kartini Nuclear Reactor by Monte Carlo N-Particle Extended (MCNPX) Simulation Method
Boron Neutron Capture Therapy (BNCT) on radial piercing beam port Kartini nuclear reactor by MCNPX simulation method has been done in the National Nuclear Energy Agency Yogyakarta. BNCT is a type of therapy alternative that uses nuclear reaction 10B (n, α) 7Li to produce 2.79 MeV total kinetic energy. To be eligible IAEA conducted a study of design improvements and variations on some parameters to optimum condition which are Ni-nat thickness of 1.75 cm as collimator wall, Al2S3 as thick as 29 cm as moderator, Al2O3 0.5 cm thick as filter, Pb and Bi thickness of 4 cm as the end of the gamma shield collimators and Bi thickness of 1.5 cm as the base gamma shield collimators. The total dose was accepted in the tumor tissue 900 × 10-4 Gy/s. Radiation dose on the tumor tissue is 50±3 Gy with time irradiation of 9 minutes and 10 seconds. That dose was given into skin tissue and healthy liver tissue consecutively (6.00±0.05) × 10-2 Gy and (10.00±0.05) × 10-2 Gy. It shows the dose received by healthy tissue is still within safe limits.
Anonymous B., 2014, Radiation Therapy and You, National Cancer Institute, USA.
Fujii, H., Matsuyama, A., Komoda, H., Sasai, M., Asano, T., Doki, Y., Kirihata, M., Ono, K., Tabata, Y., Kaneda, Y., Sawa, Y. and lee, C.M., 2011, Cationized gelatin-HVJ envelope with sodium borocaptate improved the BNCT efficacy for liver tumor in vivo, Radiation Oncology, 6:8.
International Commision on Radiations Unit and Measurements Report 44, 1989, Dokumen Teknis. USA.
Konijnenberg, M.W., Bijster, M., Krenning, E.P. and de Jong, M., 2004, 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, The Journal of Nuclear Medicine, vol. 45, page. 1260-1269.
Liu, Y.H., Lee, P.Y., Lin, Y.C., Chou, F.I., Chen, W.L., Huang, Y.S. and Jiang, S.H., 2014, Dose estimation of animal experiments at the THOR BNCT beam by NCTPlan and Xplan, Applied Radiation and Isotopes, vol.88, page. 125-128.
Siegel, R., Ma, J., Zou, Z. and Jemal, A., 2014, Cancer Statistics 2014, CA Cancer J Clinical, vol. 64, page. 9-29.
Soppera, N., Dupont, E. and Bossant, M., 2012, Java-based Nuclear Information Software: Book of Neutron-induced Cross-section, A technical document, Nuclear Energy Agency, Issy-les-Moulineaux.
Wahyuningsih, D., 2014, Optimasi Desain Kolimator Untuk Uji In Vivo Boron Capture Therapy (BNCT) pada Beam port Tembus reaktor Kartini Menggunakan Simulasi Monte Carlo Partikel 5 (MCNP5), Tesis, Universitas Gadjah Mada, Yogyakarta.
Widarto, 2002, Analisis dan Penentuan Distribusi Fluks Neutron Saluran Tembus Radial untuk Pendayagunaan Reaktor Kartini, Ganendra, vol.V, No.1, ISSN page. 1410-6957.
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Indonesian Journal of Physics and Nuclear Applications is licensed under a Creative Commons Attribution 4.0 International License.