Characteristics of Paraffin Shielding of Kartini Reactor, Yogyakarta
Vol. 35 No. 3 (2018), Research Article
Vol. 35 No. 3 (2018)

Characteristics of Paraffin Shielding of Kartini Reactor, Yogyakarta

Research Article
https://doi.org/10.29037/ajstd.526
Published 2018-12-24 — Updated on 2020-07-17
Lana Khanifah
Department of Physics, Faculty of Mathematics and Natural Sciences, Universitas Negeri Semarang, Semarang 50229, Indonesia
Susilo Widodo
Center of Accelerator Science and Technology, National Nuclear Energy Agency, Yogyakarta 55281, Indonesia
Widarto
Center of Accelerator Science and Technology, National Nuclear Energy Agency, Yogyakarta 55281, Indonesia
Ngurah Made Dharma Putra
Department of Physics, Faculty of Mathematics and Natural Sciences, Universitas Negeri Semarang, Semarang 50229, Indonesia
Argo Satrio
Center of Accelerator Science and Technology, National Nuclear Energy Agency, Yogyakarta 55281, Indonesia
AJSTD 35(3)
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Keywords

BNCT
Paraffin
Radiation shielding

Abstract

The National Nuclear Energy Agency (BATAN) Yogyakarta uses two kinds of paraffin for shielding radiation of Kartini reactor. For developing BNCT research, the radiation attenuation capability of paraffin has been analyzed to find out the coefficient attenuation, density, and composition of both kinds of paraffin. The components of the paraffin were analyzed using Fourier transform infrared (FTIR) spectroscopy, scanning electron microscopy (SEM), and energy dispersive X-ray (EDX) spectroscopy characterization. Paraffin P1 has a density of 0.689 gr/mL and paraffin P2 is 0.578 gr/mL. Paraffin samples P1 and P2 were the sample content of functional group CH, CH2, and OH when analyzed by FTIR. Paraffin P2 had an additional content namely CO. The concentration of carbon (C) and oxide (O) of paraffin P2 was much greater than that of paraffin P1. Hydrogen (H) in the paraffin has the function of moderating neutrons, but hydrogen content in both kinds of paraffin could not be detected by EDX. The acquired neutron coefficient attenuation of paraffin P2 was 0.0382 cm-1 and the gamma coefficient attenuation was 0.0535 cm-1.

https://doi.org/10.29037/ajstd.526
pdf

References

Aygün B, Korkut T, Karabulut A, Gencel O, Karabulut A.2015. Production and neutron irradiation tests on a new epoxy/molybdenum composite. Int J Polym Anal Charact. 20(4):323–329. doi:10.1080/1023666X.2015.101779.

Buyuk B, Tugrul AB. 2014. Gamma and neutron attenuation behaviours of boron carbide–silicon carbide composites. Ann Nucl Energy. 71:46–51. doi:10.1016/j.anucene.2014.03.026.

Ding W, Nan HJ, Wu TF, Guo T, Wang BR, Shen RQ. 2015. Detector shielding materials for fast neutron analysis system. Mater Res Innovations. 19(sup5):S5–870–S5–873.doi:10.1179/1432891714Z.0000000001210.

Kankaanranta L, Seppälä T, Koivunoro H, Saarilahti K, Atula T, Collan J, Salli E, Kortesniemi M, Uusi-Simola J,Välimäki P, et al. 2012. Boron neutron capture therapy in the treatment of locally recurred head-and-neck cancer:Final analysis of a phase I/II trial. Int J Radiat Oncol Biol Phys. 82(1):e67–e75. doi:10.1016/J.IJROBP.2010.09.057.

Piotrowski T, Mazgaj M, ?ak A, Skubalski J. 2015. Importance of atomic composition and moisture content of cement based composites in neutron radiation shielding. Procedia Eng. 108:616–623. doi:10.1016/J.PROENG.2015.06.188.

Yura Y, Fujita Y. 2013. Boron neutron capture therapy as anovel modality of radiotherapy for oral cancer: Principle and antitumor effect. Oral Sci Int. 10(1):9–14. doi:10.1016/S1348-8643(12)00046-8.
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