COMBINED METHOD OF BULK MATERIAL SHIELDING EVALUATION FOR 200 MEV HIGH ENERGY NEUTRON SOURCE USING PHITS MODELLING AND PARTIAL DENSITY
DOI:
https://doi.org/10.21009/SPEKTRA.081.01Keywords:
shielding, monte carlo, neutron, radiation protection, partial densityAbstract
Neutron encounters difficulties in shielding protection. Thus, many researchers have performed simulation and experimental research on neutron shielding materials. The characteristic of materials is highly dependent on neutron energy. The evaluation of neutron shielding for various materials, such as iron, concrete, aluminum, and borated polyethylene (BPE), was conducted in this paper through simulation using a Monte Carlo code of PHITS 3.27 and calculation via partial density method. A mono-energetic neutron source with an energy of 200 MeV is emitted perpendicular to the shielding material with a thickness of 105 cm. The parameters measured in this analysis include flux, fast neutron removal cross-section, neutron depth dose, ambient dose H*(10) equivalent, and neutron dose reduction factor (RF). Results show that iron is a good material against high-energy neutron and secondary photon radiation at the energy range with the highest removal cross-section and the lowest RF value (0.39), followed by concrete, BPE, and aluminum. The integrated fluence and effective dose profiles were consistent with previous results in the literature. Benchmarking calculation of neutron dose RF was conducted with other publications and was in good agreement within the value range.
References
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[48] Wu, Hwai-Chung and C. D. Eamon, “Strengthening of concrete structures using fiber reinforced polymers (FRP): design, construction and practical applications,” 2017.
[2] H. Paganetti, “Proton Therapy Physics,” Second Edition. Series in Medical Physics and Biomedical Engineering, Boca Raton, New York: CRC Press, Taylor & Francis Group, 2019.
[3] J. Y. J. Wei, “Neutrons in Proton Therapy: Quantifying the spatial and angular distribution of lethal neutrons for treatment planning,” National University of Singapore, 2019.
[4] G. F. Garcia-Fernandez et al., “Neutron dosimetry and shielding verification in commissioning of Compact Proton Therapy Centers (CPTC) using MCNP6.2 Monte Carlo code,” Applied Radiation and Isotopes, vol. 169, p. 109279, 2021, doi: 10.1016/j.apradiso.2020.109279.
[5] W. D. Newhauser and R. Zhang, “The physics of proton therapy,” Physics in Medicine & Biology, vol. 60, no. 8, pp. R155-R209, 2015, doi: 10.1088/0031-9155/60/8/R155.
[6] E. Mansouri et al., “A review on neutron shielding performance of nanocomposite materials,” International Journal of Radiation Research, vol. 18, no. 4, pp. 611-622, 2020, doi: 10.18869/acadpub.ijrr.18.4.611.
[7] PTCOG, “Practice Considerations for Proton Beam Radiation Therapy of Uveal Melanoma During the Coronavirus Disease Pandemic,” Particle Therapy Co-operative Group, 2020, [Online], Available: https://www.ptcog.ch/.
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[12] M. Fragopoulou and M. Zamani, “Phenomenological calculations of shielding spallation neutron sources,” Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, vol. 714, pp. 24-30, 2013, doi: 10.1016/j.nima.2013.02.023.
[13] T. Piotrowski, “Neutron shielding evaluation of concretes and mortars: A review,” Construction and Building Materials, vol. 277, p. 122238, 2021, doi: 10.1016/j.conbuildmat.2020.122238.
[14] S. Hashimoto et al., “PHITS Simulation of Quasi-Monoenergetic Neutron Sources from 7Li(p,n) Reactions,” Energy Procedia, vol. 71, pp. 191-196, 2015, doi: 10.1016/j.egypro.2014.11.869.
[15] T. Sato et al., “Features of Particle and Heavy Ion Transport code System (PHITS) version 3.02,” Journal of Nuclear Science and Technology, vol. 55, no. 6, pp. 684-690, 2018, doi: 10.1080/00223131.2017.1419890.
[16] J. W. Shin et al., “GEANT4 and PHITS simulations of the shielding of neutrons from the 252Cf source,” Journal of the Korean Physical Societ, vol. 65, no. 5, pp. 591-598, 2014, doi: 10.3938/jkps.65.591.
[17] S. F. Olukotun et al., “The effect of incorporated recycled low density polyethylene (LDPE) on the fast neutron shielding behaviour (FNSB) of clay matrix using MCNP and PHITS Monte Carlo codes,” Radiation Physics and Chemistry, vol. 182, p. 109351, 2021, doi: 10.1016/j.radphyschem.2021.109351.
[18] X. Zhang et al., “Benchmarking GEANT4 and PHITS for 14.8-MeV neutron transport in polyethylene and graphite materials,” Fusion Engineering and Design, vol. 170, p. 112720, 2021, doi: 10.1016/j.fusengdes.2021.112720.
[19] Y. Iwamoto et al., “Measurements and Monte Carlo calculations of forward-angle secondary-neutron-production cross-sections for 137 and 200 MeV proton-induced reactions in carbon,” Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, vol. 690, pp. 1-16, 2012, doi: 10.1016/j.nima.2012.06.038.
[20] H. Iwamoto and S. I. Meigo, “Validation of PHITS Spallation Models from the Perspective of the Shielding Design of Transmutation Experimental Facility,” EPJ Web of Conferences, vol. 153, pp. 1-9, 2017, doi: 10.1051/epjconf/201715301016.
[21] F. Cadini et al., “Neutron shielding for a new projected proton therapy facility: A Geant4 simulation study,” Physica Medica, vol. 32, no. 12, pp. 1862-1871, 2016, doi: 10.1016/j.ejmp.2016.12.003.
[22] D. R. McAlister, “Neutron Shielding Materials,” University Lane Lisle USA, 2016.
[23] A. Glovebox, S. Annual and C. Dees, “Neutron Radiation Shielding Strategies for Glovebox Applications,” Idaho National Lab, United States, 2017.
[24] Y. Zuo et al., “Monte Carlo optimization simulation of neutron shielding performance of iron/polyethylene combined structure,” MATEC Web of Conferences, vol. 189, p. 02001, 2018, doi: 10.1051/matecconf/201818902001.
[25] G. Hu et al., “New shielding material development for compact accelerator-driven neutron source,” AIP Advances, vol. 7, no. 4, p. 045213, 2017, doi: 10.1063/1.4982241.
[26] F. Tovesson and T. S. Hill, “Neutron induced fission cross section of 237Np from 100 keV to 200 MeV,” Physical Review C, vol. 75, no. 3, p. 34610, 2007, doi: 10.1103/PhysRevC.75.034610.
[27] T. Koi et al., “Attenuation of neutrons in the atmosphere and a thick carbon target,” Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, vol. 469, no. 1, pp. 63-69, 2001, doi: 10.1016/S0168-9002(01)00289-3.
[28] V. P. Singh and N. M. Badiger, “Gamma ray and neutron shielding properties of some alloy materials,” Annals of Nuclear Energy, vol. 64, pp. 301-310, 2014, doi: 10.1016/j.anucene.2013.10.003.
[29] S. Agosteo et al., “Shielding data for 100-250 MeV proton accelerators: Double differential neutron distributions and attenuation in concrete,” Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, vol. 265, no. 2, pp. 581-598, 2007, doi: 10.1016/j.nimb.2007.09.046.
[30] S. Agosteo, M. Magistris, A. Mereghetti, M. Silari, and Z. Zajacova, “Shielding data for 100-250 MeV proton accelerators: Attenuation of secondary radiation in thick iron and concrete/iron shields,” Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, vol. 266, no. 15, pp. 3406-3416, 2008, doi: 10.1016/j.nimb.2008.05.002.
[31] G. Zhang, “Monte Carlo Simulation of Mixed Neutron-Gamma Radiation Fields and Dosimetry Devices,” pp. 1-150, 2011.
[32] J. S. Alzahrani et al., “Simulating the radiation shielding properties of TeO2–Na2O–TiO glass system using PHITS Monte Carlo code,” Computational Materials Science, vol. 196, p. 110566, 2021, doi: 10.1016/j.commatsci.2021.110566.
[33] A. F. Bielajew, “Fundamentals of the Monte Carlo method for neutral and charged particle transport,” The University of Michigan, 2020.
[34] T. R. Ayodele, “Analysis of Monte Carlo Simulation Sampling Generator- Connected Power System,” Journal English Science Technology, vol. 11, no. 4, pp. 563-583, 2016.
[35] B. Harding, C. Tremblay and D. Cousineau, “Standard errors: A review and evaluation of standard error estimators using Monte Carlo simulations,” The Quantitative Methods for Psychology, vol. 10, no. 2, pp. 107-123, 2014, doi: 10.20982/tqmp.10.2.p107.
[36] E. P. Blizard et al., “Atomic energy commission, Division of technical information,” Reactor handbook, London: Interscience, 1962.
[37] J. J. Duderstadt and L. J. Hamilton, “Nuclear Reactor Analysis.” John Wiley & Sons, New York, USA, 1976.
[38] Y. Elmahroug, B. Tellili and C. Souga, “Determination of shielding parameters for different types of resins,” Annals of Nuclear Energy, vol. 63, pp. 619-623, 2014, doi: 10.1016/j.anucene.2013.09.007.
[39] M. F. Kaplan, “Concrete radiation shielding: nuclear physics, concrete properties, design and construction,” Harlow; New York: Longman Scientific & Technical ; Wiley, 1989.
[40] S. Glasstone, “Nuclear reactor engineering,” New York, NY: Chapman & Hall, 1994.
[41] W. M. Stacey, “Nuclear reactor physics,” John Wiley & Sons, 2018.
[42] B. Ma et al., “Shielding design of a target station and radiation dose level investigation of proton linac for a compact accelerator-driven neutron source applied at industrial sites,” Applied Radiation and Isotopes, vol. 137, no. 28, pp. 129-138, 2018, doi: 10.1016/j.apradiso.2018.03.015.
[43] H. Yoshida-Ohuchi et al., “Reduction factors for wooden houses due to external γ-radiation based on in situ measurements after the Fukushima nuclear accident,” Scientific Reports, vol. 4, no. 1, p. 7541, 2014, doi: 10.1038/srep07541.
[44] H. Yoshida-Ohuchi, N. Matsuda and K. Saito, “Review of reduction factors by buildings for gamma radiation from radiocaesium deposited on the ground due to fallout,” Journal of environmental radioactivity, vol. 210, p. 105810, 2019, doi: 10.1016/j.jenvrad.2018.09.008.
[45] J. L. Wang et al., “Radiation shielding design of a compact single-room proton therapy based on synchrotron,” Nuclear Science and Techniques, vol. 31, no. 1, pp. 1-12, 2020, doi: 10.1007/s41365-019-0712-1.
[46] S. Weeks and A. Astin, “Protection Against Neutron Radiation Up to 30 Million Electron Volts,” Washington: National Bureau of Standards, 1957.
[47] A. F. Mkhaiber and S. K. Dawood, “Calculation of Shielding Parameters of Fast Neutrons for Some Composite Materials,” Al-Mustansiriyah Journal of Science, vol. 30, no. 1, pp. 210-215, 2019, doi: 10.23851/mjs.v30i1.520.
[48] Wu, Hwai-Chung and C. D. Eamon, “Strengthening of concrete structures using fiber reinforced polymers (FRP): design, construction and practical applications,” 2017.
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Published
2023-04-28
How to Cite
Aliyah, F., Rahman, A. A., Md Radzi, Y., & Kambali, I. (2023). COMBINED METHOD OF BULK MATERIAL SHIELDING EVALUATION FOR 200 MEV HIGH ENERGY NEUTRON SOURCE USING PHITS MODELLING AND PARTIAL DENSITY. Spektra: Jurnal Fisika Dan Aplikasinya, 8(1), 1–16. https://doi.org/10.21009/SPEKTRA.081.01
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