The Neutron Radiation Analysis On In Vitro/ In Vivo Testing Facility Boron Neutron Capture Therapy

Authors

  • Arrijalu Fadhli Robbi STTN BATAN

DOI:

https://doi.org/10.24246/ijpna.v4i3.102-107

Keywords:

Boron Neutron Capture Theraphy, Shielding, In vitro/ In vitro testing, Neutron Radiation

Abstract

Boron Neutron Capture Therapy (BNCT) is a radiotherapy method that utilizes the interaction of boron-10 and thermal neutrons that produce lithium particles and alpha particles to kill cancer cells. Before treatment is done to humans, clinical and non-clinical testing is carried out. Non-clinical testing included In Vivo and In Vitro tests. This In Vivo and In Vitro test involves the Kartini reactor as a source and guarantees that the workers and the environment are safe when the reactor is operated. This research is aimed to analyze the neutron radiation after it has passed shielding made from paraffin with aluminum casing in an in vivo/ in  vitro testing facility for BNCT. The shielding should withstand neutron radiation so that the radiation dose does not exceed the dose constraint set by PSTA-BATAN at 10 μSv/ hour.  In this research, the initial shielding design was in the form of a 2D beam arrangement. For this reason, optimization of each shielding beam form into 3D can be identified. After that, the shieldings were produced and arranged in the radial piercing beamport of Kartini Reactor. The measurement results showed  that neutron radiation exposure in the working area around shielding at all measurement points is 0 μSv/ hour , so the results of shielding design calculations can be validated. Neutron radiation exposure was found at 3.78 μSv/ hour  and 2.36 μSv/ hour  in measurements that were taken between the shielding gaps on the left and right side of the reactor's wall. These measurement results were below the prescribed dose constraint, so the working environment is safe.

Downloads

Download data is not yet available.

References

WHO. (2018, 9 12). Cancer. Retrieved 12 5, 2018, from https://www.who.int/news-room/fact-sheets/detail/cancer

Tsurayya, A. H. (2017). Pemodelan Shielding Berbahan Parafin dan Alumunium Untuk Fasilitas BNCT Menggunakan Simulator MCNP. Universitas Negeri Yogyakarta, Fakultas Matematika dan Ilmu Pengetahuan Alam. Yogyakarta: Universitas Negeri Yogyakarta.

Shaaban, I., & Albarhoum, M. (2014). Design calculation of an epithermal neutronic beam for BNCT at the Syrian MNSR using the MCNP4C code. Elsevier, 1.

Guan, X., Manabe, M., Tamaki, S., Liu, S., Sato, F., Murata, I., & Wang, T. (2016). Experimental study on the performance of an epithermal neutron flux monitor for BNCT. Applied Radiation and Isotopes, 1-2.

Moss, R. L. (2014). Critical review, with an optimistic outlook, on BNCT. Applied Radiation and Isotopes, 1-3.

Heydari, F., & Ahmadi, R. (2015). Tehran Research Reactor as a Neutron Source for Boron Neutron Capture Therapy in Iran: A Cancer Treatment Plan for Future. 1-3.

Masoudi, F., Rasouli, F., & Gasemi, M. (2017). BNCT of skin tumors using the high-energy D-T Neutron. Applied Radiation and Isotopes, 2 - 3.

Maysaroh, A. (2018). Pemodelan Desain Sistem Keselamatan Radiasi dan Dose Treatment Planning untuk Uji In Vivo BNCT Pada Beam Port Tembus Radial Reaktor Kartini Menggunakan Simulator MCNP-X. Universitas Gadjah Mada, Fakultas Matematika dan Ilmu Pengetahuan Alam. Sleman: Universitas Gadjah Mada

Widarto. (2002). Analisis dan Penentuan Distribusi Fluks Neutron Saluran Tembus Radial Untuk Pendayagunaan Reaktor Kartini. Ganendra, 1-6.

BAPETEN. (2013). Proteksi dan Keselamatan Radiasi dalam Pemanfaatan Tenaga Nuklir. Indonesia: Dokumen Teknis BAPETEN.

Prabowo, B. E. (2015). Desain Perisi Radiasi Fasilitas Uji In Vitro Boron Neutron Capture Therapy (BNCT) Beam Port Tembus Radial Reaktor Kartini Menggunakan Simulator Monte Carlo N-Particle Extended (MCNPX). Universitas Negeri Yogyakarta, Fakultas Matematika dan Ilmu Pengetahuan Alam. Sleman: Universitas Negeri Yogyakarta.

Zhang, Y., Chen, F., Tang, X., Huang, H., Ni, M., & Chen, T. (2017). Preparation and characterization of paraffin/nickel foam composites as neutron-shielding materials. JOURNAL OF COMPOSITE MATERIALS, 1-2.

Downloads

Published

2019-10-31

How to Cite

Robbi, A. F. (2019). The Neutron Radiation Analysis On In Vitro/ In Vivo Testing Facility Boron Neutron Capture Therapy. Indonesian Journal of Physics and Nuclear Applications, 4(3), 102–107. https://doi.org/10.24246/ijpna.v4i3.102-107

Issue

Section

Articles