Calculation of Fast Neutron Shielding Parameters for Some Essential Carbohydrates
Öz
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.
Anahtar Kelimeler
Kaynakça
- 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.
Ayrıntılar
Birincil Dil
İngilizce
Konular
Mühendislik
Bölüm
Araştırma Makalesi
Yazarlar
Yayımlanma Tarihi
31 Ağustos 2019
Gönderilme Tarihi
5 Temmuz 2019
Kabul Tarihi
16 Temmuz 2019
Yayımlandığı Sayı
Yıl 2019 Cilt: 12 Sayı: 2
Cited By
Fast Neutrons Shielding Properties for HAP-Fe2O3 Composite Materials
International Journal of Computational and Experimental Science and Engineering
https://doi.org/10.22399/ijcesen.1012039Computation of Neutron Coefficients for B2O3 reinforced Composite
International Journal of Computational and Experimental Science and Engineering
https://doi.org/10.22399/ijcesen.1290497Fast and Thermal Neutron Removal Cross-Section for Ceramic Glass Aluminum Oxynitride
Black Sea Journal of Engineering and Science
https://doi.org/10.34248/bsengineering.1508116Influence of Gd2O3 reinforcement on the mechanical, physical and radiation shielding properties of Al-30Sm2O3 composites
Journal of New Results in Science
https://doi.org/10.54187/jnrs.1569548Impact of Co‐doping Eu3+ and Gd3+ in HMO‐Based Glasses for Structural and Optical Properties and Radiation Shielding Enhancement
Luminescence
https://doi.org/10.1002/bio.70045Neutron shielding and activation estimation of Bismuth doped glasses (60-x) B2O3–20SiO2–x Bi2O3–12ZnO–8BaO
Nuclear Materials and Energy
https://doi.org/10.1016/j.nme.2025.101971Influence of Tb4O7 on structural, optical and gamma, charged particle and neutron shielding properties B2O3–Bi2O3–Na2O–Al2O3 glass system
Radiation Physics and Chemistry
https://doi.org/10.1016/j.radphyschem.2025.113224Bakır/Alüminyum/Demir/Antimon Alaşımlarının Gama ve Nötron Radyasyonları Zırhlama Karakteristiklerinin İncelenmesi
Osmaniye Korkut Ata Üniversitesi Fen Bilimleri Enstitüsü Dergisi
https://doi.org/10.47495/okufbed.1703058