OPTIMIZATION OF BIOLOGICAL SHIELD FOR BORON NEUTRON CAPTURE CANCER THERAPY (BNCT) AT KARTINI RESEARCH REACTOR
DOI:
https://doi.org/10.17146/tdm.2017.19.3.3626Keywords:
Radiation shielding, BNCT, MCNPX, radiation dose rate, piercing beamportAbstract
A study to optimize a model of neutron radiation shielding for BNCT facility in the irradiation room has been performed. The collimator used in this study is a predesigned collimator from earlier studies. The model includes the selection of the materials and the thickness of materials used for radiation shield. The radiation shield is required to absorb leaking radiation in order to protect workers at the threshold dose of 20 mSv/year. The considered materials were barite concrete, paraffin, stainless steel 304 and lead. The leaking neutron radiation dose rates have been determined using Monte Carlo N Particle Version Extended (MCNPX) with a radiation dose limit rate that is less than 10 µSv/hour. This dose limit is in accordance with BAPETEN regulation related the threshold dose for workers, in which the working duration is 8 hours per day and 5 days per week. It is recommended that the best model for the irradiation room has a dimension 30 cm width, 30 cm length, 30 cm height and a main layer of irradiation room shielding made from the material paraffin which is 68 cm thickness on the left side and bottom of the irradiation room, 70 cm thickness on the right side of the iradiation room, 45 cm thickness on the front of the irradiation room and 67 cm thickness on the top of the irradiation room. The additional layers of 15 cm and 10 cm thickness are used along with paraffin in order to reduce the intensity of primary radiation from piercing the beamport after two primary layers. There is no neutron radiation leakage in this model.
References
National Cancer Institute. About Cancer: What Is Cancer? [accessed: 19 November 2015]. Available from: https://www.cancer.gov/about-cancer/understanding/what-is-cancer/
Rasouli, F. S. & Masoudi, S. F. Simulation of the BNCT of Brain Tumors Using MCNP Code: Beam Designing. Iranian Journal of Medical Physics. 2012. 9(3), pp. 183-192.
Sauerwein, W. A. G. Principles and Roots of Neutron Capture Therapy. In: Neutron Capture Therapy. Essen: Springer. 2012. p. 1.
https://doi.org/10.1007/978-3-642-31334-9_1
IAEA Current Status of Neutron Capture Therapy. Vienna, Austria: International Atomic Energy Agency; 2001.
Fauziah, A. A. Conceptual Design of Neutron Collimator in Termal Column of Kartini Research Reactor for Boron Neutron Capture Therapy. Yogyakarta: Department of Engineering Physics Gadjah Mada University; 2013.
Pamungkas, V. S. H. Simulasi Rancang Bangun Kolimator pada Beam port tembus Reaktor Kartini untuk Uji In Vivo Boron Neutron Capture Therapy. Yogyakarta: Department of Physics Gadjah Mada University; 2016.
Maharani, C. Perancangan Kolimator Singgung pada Beamport Singgung Reaktor Kartini untuk Boron Neutron Capture Therapy. Yogyakarta: Department of Physics Gadjah Mada University; 2014.
Warfi, R. Optimasi Kolimator Kolom Termal untuk Fasilitas Uji In Vivo dan In Vitro Boron Neutron Capture Therapy (BNCT) di Reaktor Kartini Menggunakan Simulator MCNP-X. Yogyakarta: Department of Engineering Physics Gadjah Mada University; 2015.
Arrozaqi, M. I. M. Perancangan Kolimator di Beamport Tembus Reaktor Kartini untuk Boron Neutron Capture Therapy. Yogyakarta: Department of Engineering Physics Gadjah Mada University; 2013.
Dwiputra, M. I. M. A. Pemodelan Perisai Radiasi Fasilitas Boron Neutron Capture Therapy dengan Sumber Neutron kolom Termal Reaktor Kartini Menggunakan Simulator Monte Carlo N Particle Extended. Yogyakarta: Department of Engineering Physics Gadjah Mada University; 2015.
Santoso, B. H. Pemodelan Perisai Radiasi Fasilitas BNCT dengan Sumber Beamport Tembus Teras Reaktor Kartini Menggunakan MCNP5. Yogyakarta: Department of Engineering Physics Gadjah Mada University; 2014.
