Epoxy Based Metal And Metal Oxide Doped New Composite Neutron And Gamma Radiation Moderator Material

Öz

In this study, five different composite shield materials were developed and produced.  Epoxy resin based different proportions, materials such as [chromium oxide (Cr₂O₃), lithium florür (LiF), nickel oxide (NiO), bismuth oxide (Bi₂O₃), manganese oxide (MnO), copper oxide (CuO), titanium oxide (TiO₂), cobalt oxide (CoO), gadolinium oxide (Gd₂O₃), selit (CaWO₄), iron oxide (Fe₂O₃), lead oxide (PbO)] were used on production. The GEANT4 code of the Monte Carlo simulation program was used in determining mixing ratios. The total macroscopic cross section, mean free path and transmission neutron number were determined for fast neutron radiation by using GEANT4 simulation code. The mass attenuation coefficient and half-value layer (HVL) were calculated for gamma radiation by using WinXCom software. Experimental absorbed dose measurement was carried out and in these measurements ²⁴¹Am-Be neutron source with 74 GBq activity which average neutron energy is approximately 4.5 MeV and BF₃ gas detector were used.  Both simulation and experimental measurements were compared with paraffin, conventional concrete. It was found that the new composite shielding material absorbed radiation much better than these reference materials. It has been suggested that this new radiation shielding composite material can be used in areas such as nuclear medicine, transport and storage of radioactive waste, nuclear power plants and as shield material for both neutron and gamma radiation. 

Anahtar Kelimeler

• Neutron and gamma radiation,epoxy,GEANT4,shielding,metal oxide

Epoksi Bazlı Metal Ve Metal Oksit Katkılı Yeni Kompozit Nötron Ve Gamma Radyasyon Moderatör Malzemesi

Öz

Bu çalışmada beş farklı komposit zırh malzemesi geliştirildi ve üretildi. Üretimlerde epoksi reçinesi taban malzeme olarak farklı özelliklere sahip [krom oksit (Cr₂O₃), lityum florür (LiF), nikel oksit (NiO), bizmut oksit (Bi₂O₃), manganez oksit (MnO), bakır oksit (CuO), titanyum oksit (TiO₂), kobalt oksit (CoO), gadolinyum oksit (Gd₂O₃), şelit (CaWO₄), demir oksit (Fe₂O₃), kurşun oksit (PbO)] gibi malzemeler kullanılmıştır.

Karışım oranları Monte Carlo Simülasyon programının GEANT4 kodu kullanılarak belirlenmiştir. Hızlı nötronlar için Toplam makroskopik tesir kesiti, ortalama serbest yol ve geçen nötron sayısı GEANT4 simülasyon kodu kullanılarak belirlendi. WinXCom yazılımı kullanılarak gamma radyasyonu için kütle zayıflama katsayısı ve yarı değer kalınlıkları (HVL) hesaplandı. Deneysel absorbtion doz ölçümleri yapıldı ve bu ölçümlerde ortalama nötron enerjisinin yaklaşık 4.5 MeV, 74 GBq aktiviteye sahip ²⁴¹Am-Be nötron kaynağı ve BF₃ gazlı dedektör kullanıldı. Hem simülasyon hem de deneysel ölçümler, geleneksel beton ve parafin ile karşılaştırıldı. Yeni kompozit zırh malzemelerinin bu referans malzemelerden çok daha iyi radyasyon emdiği tespit edildi. Bu yeni radyasyon zırh kompozit malzemelerin nükleer tıpta, radyoaktif atıkların taşınması ve depolanmasında ve nükleer santral gibi alanlarda, hem nötron hem de gama radyasyonu için kalkan malzemesi olarak kullanılabileceği önerildi.

Anahtar Kelimeler

• Nötron ve gama radyasyonu,,epoksi,,GEANT4,,zırhlama,metal oksit

Kaynakça

1. Krocher, J.F., Browman R.E., 1984. (Eds.) Reinhold New York.
2. Massingilljr, J.L., Bauer, R.S., ‘‘Applications of Epoxy Resins.’’ Applied Polymer Science 21'' Century
3. Tjong S.C., 2010. Electrical and dielectric behavior of carbon nanotube-filled polymer composites. Physical Properties and Applications of Polymer Nano composites.
4. Vovchenko L., Matzui L., Oliynyk V., Launetz V., Lazarenko A., 2008. Nanocarbon-epoxy composites as electromagnetic shielding materials. Mol. Cryst. Liq. Cryst. 497, 378–386. Zhong, W. H., Sui, G., Jana, S., Miller J., 2009.Cosmic radiation shielding tests for UHMWPE fiber=nano-epoxy composites.’’ Compos. Sci. Technol. 69, 2093–2097.
5. Li, Z., F, x., Xue, X., Jiang, T., Yang, H., Zhou, M., 2011. Study on the properties of boron-containing ores=epoxy composites for slow neutron shielding. Adv. Mater. Res. 203, 2767–2771.
6. Korkut, T., Gencel, O., Kam, Erol., Brostow W., 2013. X-Ray, Gamma, and Neutron Radiation Tests on Epoxy-Ferro chromium Slag Composites by Experiments and Monte Carlo Simulations. International Journal of Polymer Analysis and Characterization. 18, 224-231. Chang, L., Zhang Y., Liu, Y., Fang, J., Luan, W., Yang, X., Zhang, W., 2015. Preparation and characterization of tungsten/epoxy composites for γ-rays radiation shielding. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms. 356–357, 88-93.
7. Canel, A., Korkut, H., Korkut, T., 2019. Improving neutron and gamma flexible shielding by adding medium-heavy metal powder to epoxy based composite materials.’’ Radiation Physics and Chemistry 158, 13-16.
8. Fang, L., Zheng, L., Ning, W., Zhao, Z., Wang, L., 2018. Effects of γ-Ray Irradiation on the Fatigue Strength, Thermal Conductivities and Thermal Stabilities of the Glass Fibres/Epoxy Resins Composites.’’ Acta Metallurgica Sinica. 31, 105–112.

9. Agostinelli, S. et al., 2003. Geant4 simulation toolkit Nuclear Instruments and Methods in Physics Research A, 506, 250- 303.
10. Allison, J., Amako, K., et al., 2006. Geant4 developments and applications.IEEE Trans. Nucl. Sci. 53, 270–278. Mclane, V., Charles, L., Dunford, P., Rose, F., 1988. Neutron Cross Sections.’’ ISBN 978-0-12-484, 220-5.
11. Rinard, P., 1991. Neutron Interactions with Matter Passive Nondestructive Assay of Nuclear Materials.
12. Berger, M.J., Hubbell, J.H., 1987. XCOM. Photon Cross Sections Database, http://physics.nist.gov/xcom National Institute of Standard Sand Technology. Gaithersburg, MD 20899, USA. as NBSIR 87-3597 “XCOM:Photon Cross Sections on a Personal Computer. 99.
13. Singh, VP., Badiger, N.M., Chanthima, N., Kaewkhao, J., 2014. Evaluation of gamma-ray exposure buildup factors and neutron shielding for bismuth boro silicate glasses.’’ Radiat. Phys. Chem. 14- 21.
14. Sayyed, M.I., Akman, F., Turan, V., Araz, A., 2019. Evaluation of radiation absorption capacity of some soil samples. Radiochim. Acta; 107, 83- 93.
15. Sayyed, M.I., 2017. Half value layer, mean free path and exposure buildup factor for tellurite glasses with different oxide compositions.’’ Journal of Alloys and Compounds. 695, 3191-3197. Ott, K. O., W A., 1989. Bezella Introductory Nuclear Reactor Statics.’’ American Nuclear Society, Revised edition ISBN: 0 894, 48033-2.