Nuclear Engineering and Technology

  • 제51권5호
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  • Pages.1444-1450
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  • 2019
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Neutron-shielding behaviour investigations of some clay-materials

  • Olukotun, S.F. (Department of Physics and Engineering Physics, Obafemi Awolowo University) ;
  • Mann, Kulwinder Singh (Department of Physics, D.A.V College) ;
  • Gbenu, S.T. (Centre for Energy Research and Development (CERD), Obafemi Awolowo University) ;
  • Ibitoye, F.I. (Centre for Energy Research and Development (CERD), Obafemi Awolowo University) ;
  • Oladejo, O.F. (Department of Mathematical and Physical Science, Osun State University) ;
  • Joshi, Amit (Department of Physics, Guru-Kashi University) ;
  • Tekin, H.O. (Radiotherapy Department, Uskudar University, Vocational School of Health Services) ;
  • Sayyed, M.I. (Physics Department, Faculty of Science, University of Tabuk) ;
  • Fasasi, M.K. (Centre for Energy Research and Development (CERD), Obafemi Awolowo University) ;
  • Balogun, F.A. (Centre for Energy Research and Development (CERD), Obafemi Awolowo University) ;
  • Korkut, Turgay (Department of Nuclear Energy Engineering, Faculty of Engineering, Sinop University)
  • 투고 : 2017.12.23
  • 심사 : 2019.03.31
  • 발행 : 2019.06.25
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초록

The fast-neutron shielding behaviour (FNSB) of two clay-materials (Ball clay and Kaolin)of Southwestern Nigeria ($7.49^{\circ}N$, $4.55^{\circ}E$) have been investigated using effective removal cross section, ${\Sigma}_R(cm^{-1})$, mass removal cross section, ${\Sigma}_{R/{\rho}}(cm^2g^{-1})$ and Mean free path, ${\lambda}$ (cm). These parameters decide neutron shielding behaviour of any material. A computer program - WinNC-Toolkit has been used for computation of these parameters. The toolkit evaluates these parameters by using elemental compositions and densities of samples. The proficiency of WinNC-Toolkit code was probe by using MCNPX and GEANT4 to model fast neutron transmission of the samples under narrow beam geometry, intending to represent the actual experimental setup. Direct calculation of effective removal cross section ($cm^{-1}$) of the samples was also carried out. The results from each of the methods for each types of the studied clay-materials (Ball clay and Kaolin) shows similar trend. The trend might be the fingerprint of water content retained in each of the samples being baked at different temperature. The compositions of each sample have been obtained by Particle-Induced X-ray Emission (PIXE) technique (Tandem Pelletron Accelerator: 1.7 MV, Model 5SDH). The FNSB of the selected clay-materials have been compared with standard concrete. The cognizance of various factors such as availability, thermo-chemical stability and water retaining ability by the clay-samples can be analyzed for efficacy of the material for their FNSB.

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참고문헌

  1. IAEA, Harmony - the future of electricity, IAEA Bull. 25 (November 2017) 24-25.
  2. E.J. Hall, Radiobiology for the Radiologist, fifth ed., Lippincott williams & wilkins, Philadephia, 2000. New Yoke.
  3. J.E. Turner, Atoms, Radiation and Radiation Protection, third ed., John wiley and sons, New York, 2007.
  4. G.F. Knoll, Radiation Detection and Measurement, third ed., John wiley and sons, New York, 2000.
  5. R.D. Evans, in: THM (Ed.), The Atom Nucleus, McGraw-Hill, New York, 1995.
  6. E.P. Miller, Radiation Attenuation Characteristics of Structural Concrete, OAK RIDGE NATIONAL LABORATORY, Tennessee, 1958.
  7. E. Yilmaz, et al., Gamma ray and neutron-shielding properties of some concrete materials, Ann. Nucl. Energy 38 (2011) 2204-2212. https://doi.org/10.1016/j.anucene.2011.06.011
  8. A.M. El-Khayatt, NXcom - a program for calculating attenuation coefficients of fast-neutrons, Ann. Nucl. Energy 38 (2011) 128-132. https://doi.org/10.1016/j.anucene.2010.08.003
  9. N.A. Alallak, Factors affecting gamma ray transmission, Jordan J. Phys. 5 (2012) 77-88.
  10. K.S. Mann, Gamma-ray shielding behaviours of some nuclear engineering materials, Nucl. Eng. Tech. 49 (2017) 792-800. https://doi.org/10.1016/j.net.2016.12.016
  11. Oak ridge national laboratory, Early Test Facilities and Analytic Methods. Special Session Radiation Protection and Shielding, US, Department of energy, Chicago, 1992, pp. 1-8.
  12. S.A. Agbalajobi, Analysis on some physical and chemical properties of Oreke dolomite deposit, J. Miner. Mater. Charact. Eng. 1 (2013) 33-38. https://doi.org/10.4236/jmmce.2013.12007
  13. J.A. Omotoyinbo, Working properties of some selected refractory clay deposits in southwestern Nigeria, J. Miner. Mater. Charact. Eng. 7 (2008) 233-245. https://doi.org/10.4236/jmmce.2008.73018
  14. O.S. Adegoke, Guide to the Non-metal Mineral Industrial Potential of Nigeria. Raw Materials Research and Development Council, RMRDC, Kaduna, Nigeria, 1980, pp. 110-120.
  15. K.S. Mann, Fast-neutron removal cross-section calculations: computer program, Int. J. Appl. Innovat. Eng. Manag. 6 (2015).
  16. MCNP X-5, A General Monte Carlo N-Particle Transport Code: V. 5, vol. I (LA-UR-03-1987) and vol. II (LACP-0245), Los Alamos National Laboratory, 2003.
  17. A.N. Solovyev, et al., Comparative analysis of MCNPX and GEANT4 codes for fast-neutron radiation treatment planning, Nucl. Energy Technol. 1 (2015) 14-19. https://doi.org/10.1016/j.nucet.2015.11.004
  18. M.F. Kaplan, Concrete Radiation Shielding, Wiley, New York, 1989.
  19. Y. Elmahroug, Calculation of fast-neutron removal cross-sections for different shielding materials, Int. J. Phys. Res. 3 (2013) 7-16.
  20. Y. Elmahroug, Calculation of gamma and neutron-shielding parameters for some materials polyethyleneased, Int. J. Phys. Res. 3 (2013) 33-40.
  21. S.M. Harjinder, Experimental investigation of clay fly-ash bricks for gammaray shielding, Nucl. Energy Technol. 48 (2016) 1230-1236. https://doi.org/10.1016/j.net.2016.04.001
  22. M.J. Berger, J.H. Hubbell, WinXCom Software, Version 1.0.1, 1999.
  23. S.G. Sesonske, Nuclear Reactor Engineering, fourth ed., Chapman & Hall Inc, London, 1994.
  24. Geant4: a toolkit for the simulation of the passage of particles through matter, Available at: http://geant4.cern.ch/.
  25. A.E. Profio, Radiation Shielding and Dosimetry, Wiley, New York, 1982.
  26. J. Banks, Discrete-Event System Simulation, Prentice Hall, 2001, ISBN 0-13-088702-1, p. 3.
  27. H.O. Tekin, V.P. Singh, T. Manici, Effects of micro-sized and nano-sized $WO_3$ on mass attenuation coefficients of concrete by using MCNPX code, Appl. Radiat. Isot. 121 (2017) 122-125. https://doi.org/10.1016/j.apradiso.2016.12.040.
  28. H.O. Tekin, T. Manici, Simulations of mass attenuation coefficients for shielding materials using the MCNP-X code, Nuclear Science and Techniques. NUCL SCI TECH 28 (2017) 95, https://doi.org/10.1007/s41365-017-0253-4.
  29. G. Lakshminarayana, S.O. Baki, Kawa M. Kaky, M.I. Sayyed, H.O. Tekin, A. Lira, I.V. Kityk, M.A. Mahdi, Investigation of structural, thermal properties and shielding parameters for multi-component borate glasses for gamma and neutron radiation shielding applications, J. Non-Cryst. Solids (2017). https://doi.org/10.1016/j.jnoncrysol.2017.06.001.
  30. M.G. Dong, E. El-Mallawany, M.I. Sayyed, H.O. Tekin, Shielding properties of 80TeO2-5TiO2-(15-x) WO3-xAnOmglassesusingWinXComand MCNP5 code, Radiat. Phys. Chem. 141 (2017) 172-178. https://doi.org/10.1016/j.radphyschem.2017.07.006.
  31. H.O. Tekin, M.I. Sayyed, Shams A.M. Issa, Gamma radiation shielding properties of the hematite-serpentine concrete blended with $WO_3$ and $Bi_2O_3$ micro and nanoparticles using MCNPX code, RadiationPhysicsandChemistry 150 (2018) 95-100. https://doi.org/10.1016/j.radphyschem.2018.05.002.
  32. M.I. Sayyed, H.O. Tekin, O. Kilicoglu, O. Agar, M.H.M. Zaid, Shielding features of concrete types containing sepiolite mineral: comprehensive study on experimental, XCOM and MCNPX results, Results in Physics 11 (2018) 40-45. https://doi.org/10.1016/j.rinp.2018.08.029.
  33. M.I. Sayyed, Y.S. Rammah, A.S. Abouhaswa, H.O. Tekin, B.O. Elbashir, ZnO-B2O3-PbO glasses: synthesis and radiation shielding characterization, Physica B: Phys. Condens. Matter (15 August 2018). Available Online, https://doi.org/10.1016/j.physb.2018.08.024.
  34. J. Allison, et al., Geant4 developments and applications, IEEE Trans. Nucl. Sci. 53 (1) (2006) 270-278. https://doi.org/10.1109/TNS.2006.869826
  35. K. Amako, et al., Comparison of Geant4 electromagnetic physics models against NIST reference data, IEEE Trans. Nucl. Sci. 52 (4) (2005) 218-910.
  36. S. Jan, et al., GATE: a simulation toolkit for PET and SPECT, Phys. Med. Biol. 49 (2004) 4543-4561. https://doi.org/10.1088/0031-9155/49/19/007
  37. G. Santin, V. Ivanchenko, et al., GRAS: a general-purpose 3-D modular simulation tool for space environment effect analysis, IEEE Trans. Nucl. Sci. 52 (6) (2005) 2294-2299. https://doi.org/10.1109/TNS.2005.860749
  38. E. Nnuka, C. Enejor, Characterisation of Nahuta clay for industrial and commercial applications, Niger. J. Eng. Mater. 2 (2001) 9-12.
  39. J.H. Chester, Refractories, Production and Properties, The Iron and Steel Institute, London, 1973, pp. 4-13, 295-315.
  40. I.I. Bashter, Calculation of radiation attenuation coefficients for shielding concretes, Ann. Nucl. Energy 24 (1997) 1389-1401. https://doi.org/10.1016/S0306-4549(97)00003-0
  41. B.M. van der Ende, et al., Use of GEANT4 vs. MCNPX for the characterization of a boron-lined neutron detector, Nucl. Instrum. Methods Phys. Res. 820 (2016) 40-47. https://doi.org/10.1016/j.nima.2016.02.082

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