Preparation and Thermal/Fast Neutron Shielding Properties of Novel Boron Containing Ore Composites

Abstract:

Four novel boron containing ores/epoxy composites were prepared by using nature ludwigite green ore (NLGO), artificial ores including boron containing iron ore concentrate (BCIOC), boron rich slag (BRS) and boron mud (BM) as neutron absorbers, which were obtained by dressing from NLGO, blast furnace separation from BCIOC and borax production, respectively. The microstructure of the composites was investigated by X-ray diffraction (XRD), scanning electron microscope (SEM) and Fourier transform infrared spectroscopy (FT-IR). Shielding properties of the composites against thermal and Cf-252 fast neutron were measured. Factors affecting the shielding properties were investigated. Energy deposition, absorbed dose and half value layers of the composites against neutron penetration were simulated by Monte Carlo method, and a simulated function was obtained. The results showed that the composites were compact and the particles of ores were homogeneous. Ascending boron mole numbers per unit volume (n_B) in the composites can obviously enhance the macroscopic absorbing cross section (Σ_thermal) and improve the shielding properties for thermal neutron. The relationship of Σ_thermal and n_B follows the equation of Σ_thermal=0.218+450.490n_B. And the relationship of average atomic number (Z) of boron containing ores composites and the macroscopic removal cross section for fast neutron follows the equation of Σ_removal=0.042exp (-Z/5.70)+0.032. Enhancement of the shielding abilities against Cf-252 fast neutron can be achieved by using the composites with low average atomic number.

• Periodical: Materials Science Forum (Volumes 743-744)
• Pages: 613-622
• DOI: https://doi.org/10.4028/www.scientific.net/MSF.743-744.613
• Online since: January 2013
• Authors: Zhe Fu Li, Xiang Xin Xue, Pei Ning Duan, Ang Tian, Shu Xian Li, Zheng Shuai Yin
• Keywords: Average Atomic Number, Boron Containing Ores Composite, Boron Mole Number, Macroscopic Cross Section, Monte-Carlo Method (MC-Method)

References

[1] L. Shengkang, Neutron Physics, Atomic Energy Press, Beijing, (1986).

[2] S. M. Atsuhiko, A. Yoshimasa, O. Koichi, et al, Flexible heat resistant neutron shielding resin, J Nucl Mater, 417 (2011) 850-853.

[3] T. Hayashi, K. Tobita, Y. Nakamori, et al Advanced neutron shielding material using zirconium borohydride and zirconium hydride, J Nucl Mater, 386-388 (2009) 119-121.

DOI: 10.1016/j.jnucmat.2008.12.073

[4] M. Atsuhiko, S. Shinji, O. Koichi, et al. Development of 300 °C heat resistant boron-loaded resin for neutron shielding, J Nucl Mater, 367–370 (2007) 1085-1089.

[5] K. Turgay, K. Abdulhalik, B. Gökhan, et al, Investigation of neutron shielding properties depending on number of boron atoms for colemanite, ulexite and tincal ores by experiments and FLUKA Monte Carlo simulations, Appl Radiat Isot, 70 (2012).

DOI: 10.1016/j.apradiso.2011.09.006

[6] O. Koichi, Neutron shielding material based on colemanite and epoxy resin, Radiat Prot Dosim, 115(1-4) (2005) 258-261.

DOI: 10.1093/rpd/nci154

[7] K. Turgay, Ü. Adem, D. Faruk, et al, Neutron dose transmission measurements for several new concrete samples including colemanite, Ann Nucl Energy, 37 (2010) 996-998.

DOI: 10.1016/j.anucene.2010.04.005

[8] L. Su-lan, C. Chuan-meng, Z. Xian-peng, Pyrometallurgical separation of boron from iron in ludwigite ore, ISIJ Int. 38 (1998) 1077-1079.

DOI: 10.2355/isijinternational.38.1077

[9] H. Hua-si, W. Qun-shu, Q. Juan, et al, Study on composite material for shielding mixed neutron and γ-rays, IEEE Trans on Nucl Sci. 55 (4) (2008) 2376-2384.

[10] L. Zhe-fu, X. Xiang-xin, Mass attenuation coefficients of photon in boron-containing ores and epoxy, At Energy Sci Technol, 45 (2011) 1147-1152.

[11] L. Zhe-fu, X. Xiang-xin, Neutron shielding properties of boron-containing ore and epoxy composites, At Energy Sci Technol, 45 (2011) 223-229.

[12] L. Zhe-fu, X. Xiang-xin, Shielding properties of boron-containing ores composites for 1keV, 1eV and 0. 0253eV neutron, J Northeastern Univ, 32 (2011) 1716-1720.

[13] L. Zhe-fu, X. Xiang-xin, J. Tao, et al, Study on the properties of boron-containing ores/epoxy composites for slow neutron shielding, Adv Mater Res. 201/202/203 (2011) 2767-2771.

DOI: 10.4028/www.scientific.net/amr.201-203.2767

[14] L. Zhe-fu, X. Xiang-xin, J. Tao, Study on shielding properties of boron-containing iron ore concentrate powder/epoxy composite, J Funct Mater. 41 (2010) 1892-1895.