Bahan Sasaran Sebagai Sumber Neutron yang Optimal untuk Boron Neutron Capture Therapy (BNCT)
Abstract
Abstract Cancer is a deadly disease that exist on planet earth. Efforts were made to be able to kill cancer cells either by manual operation or by radiotherapy. One way to use energy radiation radioactive elements as killers of cancer cells is Boron Neutron Capture Therapy (BNCT). BNCT is a therapeutic technique that utilizes the interaction of neutron capture by the core 10B will produce α-particles and nuclei 7Li results by reaction 10B (n, α) 7Li. It therefore requires a material that will produce neutrons used in BNCT. Materials target that will be searched in order to obtain optimal materials according to the requirements provided by the International Atomic Agency (IAEA).
Keywords : Kanker, Material, Neutron, BNCT
Abstrak Kanker adalah salah satu penyakit yang mematikan yang ada di planet bumi. Upaya upaya dilakukan untuk dapat membunuh sel kanker baik itu secara operasi manual maupun dengan cara radioterapi. Salah satu cara yang memanfaatkan energi radiasi unsur unsur radioaktif sebagai pembunuh sel kanker adalah Boron Neutron Capture Therapy (BNCT). BNCT merupakan teknik terapi yang memanfaatkan interaksi tangkapan neutron oleh inti 10B yang akan menghasilkan partikel-α dan inti hasil 7Li melalui reaksi 10B(n,α) 7Li. Oleh sebab itu diperlukan material yang akan menghasilkan neutron digunakan dalam BNCT. Bahan - bahan sasaran yang akan ditelusur dalam upaya mendapatkan bahan yang optimal sesuai persyaratan yang diberikan oleh International Atomic Agency (IAEA).
Kata Kunci : Kanker, Material, Neutron, BNCT
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Ferlay, J., Soerjomataram, I., Dikshit, R., Mathers, C., Rebelo, M., Parkin, D., et al. (2014). Cancer Incidence and Mortality Worldwie. International Journal of Cancer.
Ferlay, J., Soerjomataram, I., Ervik, M., Dikshit, R., Eser, S., Mather, C., et al. (2012). Cancer Incidence and Mortality Worldwide:IARC Cancer Base No.11. IARC
IAEA. (2001). CURRENT STATUS OF NEUTRON CAPTURE THERAPY. Viena: IAEA,ISSN 1011–4289.
John, R. L., & Anthony, J. B. (t.thn.). Introduction to Nuclear Engineering. New Jersey: Pentice Hall.
Kasesaz, Y., Khalafi, H., & Rahmani, F. (2014). Design of an epithermal neutron beam for BNCT in thermal column of Tehran research reactor. Annals of Nuclear Energy, Elsevier, 234-238.
Lyon. (2013). International Agency for Research on Cancer. Dipetik Desember 2014, dari GLOBOCAN: http://globocan.iarc.fr
Tahara, Y., Oda, Y., Shiraki, T., Yokobori, H., & Nakamura, T. (2006). Engineering Design of a Spallation Reactio-Based Neutron Generator for Boron Neutron Capture Therapy. Journal of Nuclear Science and Thecnology, 43, 9-19.
Tetsuya, M., & Tetsuo, M. (2011). Progress in nuclear science and thecnology. Study on microdosimetry for boron neutron capture therapy. 2-242.
Whittmore, W. (1992). A Compact TRIGA reactor for Boron neutron capture theraphy. Progress in Neutron Capture Therapy for Cancer (hal. 57-62). New York: Plenum Press.
Wolfgang, A., Sauerwein, Pierre, M., & Andre, W. (2013). Neutron capture therapy. Drugs for BNCT. 117-161.
X-5 Monte Carlo Team. (1987). MCNP-A general Monte Carlo N-Particle Transport Code Version 5 Volume 1;Overview and Theory. Mexico: Los Alamos National Laboratory
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