Calculation of Fast Neutron Shielding Parameters for Some Essential Carbohydrates

Year 2019, Volume: 12 Issue: 2, 1141 - 1148, 31.08.2019

Hakan Akyıldırım

https://doi.org/10.18185/erzifbed.587514

Cited By: 3

Abstract

This
study is concerned with the attenuation of fast (or fission energy) neutrons by
some essential carbohydrates which carry importance for most of the living
cells. For this purpose, eleven carbohydrates having different densities have
been investigated by means fast neutron effective removal cross sections () and
attenuation lengths. The calculations have been performed using the mass
removal cross section data compiled from NCRP No. 20 (1957) and elemental
compositions of carbohydrates. The obtained results show that the Hydrogen element
plays the major role for fast neutron attenuation in selected carbohydrates. According
to our best knowledge, this could be the first study on the fast neutron
removal cross sections of selected carbohydrates. Also, the data presented here
is expected to contribute the related literature significantly.

Keywords

Neutron attenuation, fast neutron removal, attenuation length, carbohydrate.

Bazı Temel Karbonhidratlar İçin Hızlı Nötron Zırhlama Parametrelerinin Hesaplanması

Abstract

Bu çalışma, hızlı (veya fisyon
enerjili) nötronların canlı hücrelerin pek çoğu için önem taşıyan bazı temel karbonhidratlar
tarafından zayıflatılması üzerinedir. Bu amaçla, farklı yoğunluklu on bir çeşit
karbonhidrat etkin etkin hızlı nötron sökme tesir kesitleri () ve hızlı nötronları zayıflatma mesafeleri
bakımından incelenmiştir. Hesaplamalar NCRP No. 20 (1957)’den derlenen kütlesel
sökme tesir kesiti ve karbonhidratlara ait elementsel bileşim verileri
kullanılarak yapılmıştır. Elde edilen sonuçlar, seçilen karbonhidratlar içinde hızlı
nötronların zayıflatılmasında en büyük rolü Hidrojen elementinin oynadığını
göstermektedir. Bildiğimiz kadarıyla bu çalışma, hızlı nötronların seçilmiş
olan karbonhidratlara ait etkin hızlı nötron sökme tesir kesitleri üzerine
yapılan ilk çalışmadır. Ayrıca, çalışma sonucunda sunulan verilerin ilgili
literatüre kayda değer bir katkı sunacağı umulmaktadır.

Keywords

Nötron zayıflatma, hızlı nötron sökme, zayıflatma mesafesi, karbonhidrat

References

• Abdo, A.E. 2002. Calculation of the Cross-Sections for Fast Neutrons and Gamm-Rays in Concrete Shields, Annals of Nuclear Energy, 29, 1977-1988.
• Akkurt, I., El-Khayatt, A.M. 2013. The Effect of Barite Proportion on Neutron and Gamma-Ray Shielding, Annals of Nuclear Energy, 51, 5-9.
• Aygün, B., Karabulut, A. 2018. Development and Production of High Heat Resistant Heavy Concrete Shielding Materials for Neutron and Gamma Radiation, Eastern Anatolian Journal of Science, 4(2), 24-30.
• Bashter, I.I. 1997. Calculations of Radiation Attenuation Coefficients for Shielding Concretes, Annals of Nuclear Energy, 24(17), 1389-1401.
• Blizard, E.P., Abbott, L.S. 1962. Reactor Handbook, vol III, Part B, Shielding, John Wiley and Sons, Inc.
• Chilton, A.B., Shultis, J.K., Faw, R.E. 1984. Principles of Radiation Shielding, Prentice-Hall, Englewood Cliffs.
• El-Khayatt, A.M. Abdo, A.E. 2009. MERCSF-N: A Program for the Calculation of Fast Neutron Removal Cross Section in Composite Shields, Annals of Nuclear Energy, 36, 832-836.
• El-Khayatt, A.M. 2010. Radiation Shielding of Concretes Containing Sifferent Lime/Silica Ratios, Annals of Nuclear Energy, 37, 991-995.
• El-Khayatt, A.M. 2011. NXcom - A Program for Calculating Attenuation Coefficients of Fast Neutrons and Gamma-Rays, Annals of Nuclear Energy, 38, 128-132.
• El-Khayatt, A.M., Akkurt, I. 2013. Photon Interaction, Energy Absorption and Removal Cross-Section of Concrete Including Marble, Annals of Nuclear Energy, 60, 8-14.
• Elmahrough, Y., Tellili, B., Souga, C. 2014. Determination of Shielding Parameters for Different Types of Resins, Annals of Nuclear Energy, 63, 619-623.
• El-Mallawany, R., Sayyed, M.I. 2018. Comparative Shielding Properties of Some Tellurite Glasses: Part 1, Physica V: Conensed Matter, 539, 133-140.
• El-Sarrafa, M.A., Abdo, A.E. 2013. Influence of Magnetite, Ilmenite and Boron Carbide on Radiation Attenuation of Polyester Composites, Radiation Physics and Chemistry, 88, 21-26.
• Gencel, O., Bozkurt, A., Kam, E., Korkut, T. 2011. Determination and Calculation of Gamma and Neutron Shielding Characteristics of Concretes Containing Different Hematite Proportions, Annals of Nuclear Energy, 38, 2719-2723.
• Haynes, W.M., ed., CRC Handbook of Chemistry and Physics, 97th edition, CRC Press/Taylor and Francis, Boca Raton, FL.
• Issa, S.A.M., Mostafa, A.M.A., Auda, A.H. 2018. Radio-protective Properties of Some Sunblock Agents against Ionizing Radiation, Progress in Nuclear Energy, 107, 184-192.
• Jaeger, T. 1965. Principles of Radiation Protection Engineering, McGraw-Hill Book Company, New York.
• Kaplan, M. F. 1989. Concrete Radiation Shielding. Longman Scientific and Technology, Longman Group UK Limited, Essex, London.
• Korkut T., Ün, A., Demir, F., Karabulut, A., Budak, G., Şahin, R Oltulu M. 2010. Neutron Dose Transmission Measurements for Several New Concrete Samples Including Colemanite, Annals of Nuclear Energy, 37, 996-998.
• Korkut, T., Karabulut, A., Budak, G., Aygün, B., Gencel, O., Hançerlioğulları, A. 2012. Investigation of Neutron Shielding Properties Depending on Number of Boron Atoms for Colemanite, Ulexite and Tincal Ores By Experiments and FLUKA Monte Carlo Simulations, Applied Radiation and Isotopes, 70, 341-345.
• Kurudirek, M., Özdemir, Y., El-Khayat, A.M. 2011. Analysis of Some Pb, Th and U compounds in Terms of Photon Interaction, Photon Energy Absorption and Fast Neutron Attenuation, Radiation Physics and Chemistry, 80, 855-862.
• Merck. https://www.sigmaaldrich.com/catalog/product/mm/107605?lang=en&region=TR, Son erişim tarihi: 29.06.2019.
• Nair, K.P.G., Gowda, C., Kumari, J.S., Anasuya, S.J., Umesh, T.K., Gowda, R. 1993. Total Interaction Cross Sections of Several Sugars for 133Ba Photons, Nuclear Science and Engineering, 115, 300-303.
• NCRP (National Council on Radiation Protection and Measurements). 1957. Protection against Neutron Radiation up to 30 Million Electron Volts, Report No. 20, NBS Handbook, vol. 63, National Bureau of Standards, US Department of Commerce, Washington, D.C.
• Osman, A.M., El-Sarraf, M.A., Abdel-Monem, A.M., Abdo, A.E. 2015. Studying the Shielding Properties of Lead Glass Composites using Neutrons and Gamma Rays, Annals of Nuclear Energy, 78, 146-151.
• Price, B.T., Horton, C.C., Spinney, K.T. 1957. Radiation Shielding, Pergamon Press Inc., London.
• Salama, E., Maher, A., Youssef, G.M. 2019. Gamma Radiation and Neutron Shielding Properties of Transparent Alkali Borosilicate Glass Containing Lead, Journal of Physics and Chemistry of Solids, 131, 139-147.
• Schmidt, F.A.R. 1969. Analytical Radiation Shielding Calculations for Concrete – Formulas and Parameters, Nuclear Engineering and Design, 10, 308-324.
• Singh, G., Singh, K., Lark, B.S., Sahota, H.S. 2000. Attenuation Measurements in Solutions of Some Carbohydrates, Nuclear Science and Engineering, 134, 208-217.
• Singh, V.P., Badiger, N.M., Kaewkhao, J. 2014. Radiation Shielding Competence of Silicate and Borate Heavy Metal Oxide Glasses: Comparative Study, Journal of Non-Crystalline Solids, 404, 167-173.
• Singh, V.P., Medhat, M.E., Badiger, N.M., Rahman, A.Z.M.S. 2015. Radiation Shielding Effectiveness of Newly Developed Superconductors, Radiation Physics and Chemistry, 106, 175-183.
• Tellili, B., Elmahrough, Y., Souga, C. 2014. Calculation of Fast Neutron Removal Cross Sections for Different Lunar Soils, Advances in Space Research, 53, 348-352.
• Tuna, T., Bayrak, K. 2017. Investigation of the Shielding Capability of Concrete Matrixed Colemanite Reinforced Shielding Material, Journal of Engineering Technology and Applied Sciences, 2(2), 57-63.
• Wang, J., Li, G., Meng, D. 2014. Evaluation of the Performance of Peridodite Aggregates for Radiation Shielding Concrete, Annals of Nuclear Energy, 71, 436-439.
• Wieser M., Holden N., Coplen T.B., Böhlke J.K., Berlung M., Brand W.A., Bievre P., Gröning M., Loss R.D., Meija J., Hirata T., Prohaska T., Schoenberg R., O’Connor G., Walczyk T., Yoneda S., Zhu X. 2013. Atomic Weights of the Elements 2011 (IUPAC Technical Report), Pure and Applied Chemistry, 85, 1047-1078.
• Woods, J. 1982. Computational Methods in Reactor Shielding, Pergamon Press Inc., New York.
• Yarar, Y., Bayülken, A. 1994. Investigation of Neutron Shielding Efficiency and Radioactivity of Concrete Shields Containing Colemanite, Journal of Nuclear Materials, 212-215, 1720-1723.
• Yılmaz, E., Baltas, H., Kırıs, E., Ustabas, İ; Cevik, U., El-Khayatt, A.M. 2011. Gamma Ray and Neutron Shielding of Some Concrete Materials, Annals of Nuclear Energy, 38, 2204-2212.