A Modelling of Paraffin Shielding for BNCT Facility at Kartini Reactor Research using MCNPX
DOI:
https://doi.org/10.24246/ijpna.v5i2.31-37Keywords:
Shielding, Paraffin, Lead, MCNPX, Dose rate.Abstract
The development of cancer in the world is very high. According to the World Health Organization (WHO) 1.69 million people die from cancer per year in the world, while the cases of cancer in Indonesia are also not much different. Some areas have a high prevalence of cancer, namely D.I Yogyakarta. Cancer has become a scourge for many people. There are many treatments available, such as chemotherapy, surgery, and radiation. Additionally, there is radiotherapy using neutron capture of boron-10 with energy 0.025 Ev. This treatment does not damage other tissue because the resulting particles such as He-4 and Lithium-7 have ranges that are a distance of 4.5-10 μm, so that the deposited energy is limited to the diameter of a single cell. The treatment is called Boron Neutron Capture Therapy (BNCT). There are several BNCT facilities such as a reactor, radial piercing beam port, thermal column, and shielding. The function of shielding is to absorb the neutron and alpha radiation. The shielding is made using paraffin material that is excellent in absorbing neutron radiation. In addition to paraffin there are also other materials, such as lead, used as paraffin casing. In a shielding simulation using MCNPX software, the resulting dose rate of radiation exposure outside of the BNCT facility in vitro and vivo tests is equal to 6.5 μSv / h. The thickness of the shielding paraffin used is 40 cm, Pb casing 25 cm, and 5 cm soft tissue.
Downloads
References
BAPETEN, 2013, Perka BAPETEN No.4 Tahun 2013: Proteksi dan Keselamatan Radiasi dalam Pemanfaatan Tenaga Nuklir, Bapeten
Benjamin, Donald J., 2014, The efficacy of surgical treatment of cancer – 20 years later, Australia: Medical Hypotheses
Bortolussia S., 2018, Nuclear Inst. and Methods in Physics Research B, Italy: Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms
Ding, J.Colegrove, 2015, Development of a laminar flow local shielding device for wire + arc additive manufacture, Belgium: Journal of Materials Processing Technology
Elmahroug, Y., et al, Determination of shielding parameters for different types of resins, Tunisia: Annals of Nuclear Energy
Hadad, Kamal, et al, 2015, Moderation and shielding optimization for a 252Cf based prompt gamma neutron activation analyzer system, Iran: International Journal of Hydrogen Energy
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, London
Jasim, Mahdi Hadi, Abdulameer, Naji Talib, et al, 2014, Neutron Capture Cross Section, University of Baghdad: International Journal of Application or Innovation in Engineering & Management (IJAIEM)
Kageji, Teruyoshi, 2014, Boron neutron capture therapy (BNCT) for newly-diagnosed glioblastoma: Comparison of clinical results obtained with BNCT and conventional treatment, Ibaragi Japan: The Journal of Medical Investigation
Kaur, Sandeep, Singh, K. J., 2014, Investigation of lead borate glasses doped with aluminium oxide as gamma ray shielding materials, India: Annals of Nuclear Energy
Kementerian Kesehatan RI PUSAT DATA DAN INFORMASI, 2015, Stop Kanker, Jakarta Selatan: infodatin-kanker
Knoll, Glenn F. 2000. Radiation Detection and Measurement. USA: John Willey & Sons, Inc
Lai, Bo-lun, et al, 2017, Shielding analyses of an AB-BNCT facility using Monte Carlo simulations and simplified methods, Taiwan: ICRS-13 & RPSD-2016,
Lakshminarayana, G, Baki, S. O., 2017, Investigation of structural, thermal properties and shielding parameters for multicomponent borate glasses for gamma and neutron radiation shielding applications, Malaysia: Journal of Non-Crystalline Solids
Lamarsh, John R. Introduction to Nuclear Reactor Theory. 1961. New York: Addison-Wesley Publishing Company.
Made, Martinus I, Dwiputra, Adrian, et al, 2016, Shield Modelling of Boron Neutron Capture Therapy Facility with Kartini Reactor’s Thermal Column as Neutron Source using Monte Carlo N Particle Extended Simulator, Yogyakarta
Malkapur, Santhosh M, Divakar, L, 2017, Fresh and hardened properties of polymer incorporated self compacting concrete mixes for neutron radiation shielding, India: Construction and Building Materials
Moss, Raymond L., 2014, Critical review, with an optimistic outlook, on Boron Neutron Capture Therapy (BNCT), Applied Radiation and Isotopes
Nyarku, Mawutorli, et al, 2013, Experimental neutron attenuation measurements in possible fast reactor shield materialsI, Ghana: Annals of Nuclear Energy
Payudan, Aniti, et al, 2016, Basic Principle Application and Technology of Boron Neutron Capture Cancer Therapy (BNCT) Utilizing Monte Carlo N Particle 5’S Software (MCNP 5) with Compact Neutron Generator (CNG), Yogyakarta
Petrillo, V., et al, 2015, Polarization of x-gamma radiation produced by a Thomson and Compton inverse scattering, Italy: Polarization of x-gamma radiation produced by a Thomson and Compton inverse scattering
Priambodo, Gani, et al, 2017, Optimization of Biological Shield for Boron Neutron Capture Cancer Therapy (BNCT) At Kartini Research Reactor, Yogyakarta: Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega
Ródenas, José, 2017, Application of the Monte Carlo method to estimate doses due to neutron activation of different materials in a nuclear reactor, Universitat Politècnica de València Spain: Radiation Physics and Chemistry
Sardjono Yohannes, 2015, Pengantar Monte Carlo N-Particle, Yogyakarta: Jogja Bangkit Publisher
Sari, Nur Endah, et al2017, Analysis of Radiation Effects on Workers and Environment Pilot Plant Boron Neutron Capture Therapy (BNCT), Yogyakarta
Shaaban, Ismail, Albarhoum, Mohamad, 2015, Design calculation of an epithermal neutronic beam for BNCT at the Syrian MNSR using the MCNP4C code, Syiria: Progress in Nuclear Energy
Singh, Vishwanath P, Badiger, N. M., 2015, Shielding efficiency of lead borate and nickel borate glasses for gamma rays and neutrons, India: Glass Physics and Chemistry
Toyen, Donruedee, Saenboonruang, Kiadtisak, 2017, Development of paraffin and paraffin/bitumen composites with additions of B2O3 for thermal neutron shielding applications, Bangkok: Journal of Nuclear Science and Technology
Tsurayya Hana Afifah, 2017, pemodelan shielding berbahan parafin dan aluminium untuk fasilitas bnct menggunakan simulator MCNP, Yogyakarta: Universitas Negeri Yogyakarta
Waheed, Abdul, Ali, Nawab, et al, 2017, Optimization of moderator assembly for neutron
Downloads
Published
How to Cite
Issue
Section
License
Indonesian Journal of Physics and Nuclear Applications is licensed under a Creative Commons Attribution 4.0 International License.