Evaluation of shielding performance for newly developed composite materials

被引:22
作者
Evans, Beren R. [1 ]
Lian, Jie [1 ]
Ji, Wei [1 ]
机构
[1] Rensselaer Polytech Inst, Dept Mech Aerosp & Nucl Engn, 110 8th St, Troy, NY 12180 USA
关键词
Radiation shielding; Composite material; Monte Carlo simulation; Neutron photon transport; NEUTRON; RADIATION; SCIENCE; MATRIX; GAMMA;
D O I
10.1016/j.anucene.2018.01.022
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
With the advancement of fabrication technology, composite materials that consist of isotopes with different radiation interaction properties can be manufactured and used as effective radiation shielding materials. This work details an investigation into the contributing factors behind the success of newly developed composite shielding materials. Monte Carlo simulation methods were utilized to assess the shielding capabilities for neutron and the secondary radiation production characteristics in four different composite materials: aluminum boron carbide, tungsten boron carbide, bismuth borosilicate glass, and Metathene. The study is performed under neutron irradiations with various energy spectra. The resulting data regarding shielding performance and generated secondary radiation suggested that tungsten boron carbide was the most effective composite shield material. An analysis of the macroscopic cross-section contributions from constituent materials and interaction mechanisms was then performed in an attempt to better understand the relative shielding performance of the investigated composite materials. This analysis found that increased thermal absorber content was associated with improved neutron shielding performance within both the thermal and epi-thermal neutron energy regions and that composites containing low Z material demonstrated greater shielding performance within the faster neutron energy regions. (C) 2018 Elsevier Ltd. All rights reserved.
引用
收藏
页码:1 / 9
页数:9
相关论文
共 15 条
[1]   Optimization of processing parameters for the Al+10% B4C system obtained by mechanical alloying [J].
Abenojar, J. ;
Velasco, F. ;
Martinez, M. A. .
JOURNAL OF MATERIALS PROCESSING TECHNOLOGY, 2007, 184 (1-3) :441-446
[2]  
Akkas A, 2015, ACTA PHYS POL A, V128, pB176, DOI [10.12693/APhysPolA.128.B-176, 10.12693/APhysPolA.127.B-176]
[3]  
Buyuk B, 2015, ACTA PHYS POL A, V128, pB132, DOI [10.12693/APhysPolA.127.B-132, 10.12693/APhysPolA.128.B-132]
[4]   ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data [J].
Chadwick, M. B. ;
Herman, M. ;
Oblozinsky, P. ;
Dunn, M. E. ;
Danon, Y. ;
Kahler, A. C. ;
Smith, D. L. ;
Pritychenko, B. ;
Arbanas, G. ;
Arcilla, R. ;
Brewer, R. ;
Brown, D. A. ;
Capote, R. ;
Carlson, A. D. ;
Cho, Y. S. ;
Derrien, H. ;
Guber, K. ;
Hale, G. M. ;
Hoblit, S. ;
Holloway, S. ;
Johnson, T. D. ;
Kawano, T. ;
Kiedrowski, B. C. ;
Kim, H. ;
Kunieda, S. ;
Larson, N. M. ;
Leal, L. ;
Lestone, J. P. ;
Little, R. C. ;
McCutchan, E. A. ;
MacFarlane, R. E. ;
MacInnes, M. ;
Mattoon, C. M. ;
McKnight, R. D. ;
Mughabghab, S. F. ;
Nobre, G. P. A. ;
Palmiotti, G. ;
Palumbo, A. ;
Pigni, M. T. ;
Pronyaev, V. G. ;
Sayer, R. O. ;
Sonzogni, A. A. ;
Summers, N. C. ;
Talou, P. ;
Thompson, I. J. ;
Trkov, A. ;
Vogt, R. L. ;
van der Marck, S. C. ;
Wallner, A. ;
White, M. C. .
NUCLEAR DATA SHEETS, 2011, 112 (12) :2887-2996
[5]   INITIAL MCNP6 RELEASE OVERVIEW [J].
Goorley, T. ;
James, M. ;
Booth, T. ;
Brown, F. ;
Bull, J. ;
Cox, L. J. ;
Durkee, J. ;
Elson, J. ;
Fensin, M. ;
Forster, R. A. ;
Hendricks, J. ;
Hughes, H. G. ;
Johns, R. ;
Kiedrowski, B. ;
Martz, R. ;
Mashnik, S. ;
McKinney, G. ;
Pelowitz, D. ;
Prael, R. ;
Sweezy, J. ;
Waters, L. ;
Wilcox, T. ;
Zukaitis, T. .
NUCLEAR TECHNOLOGY, 2012, 180 (03) :298-315
[6]   Advanced neutron shielding material using zirconium borohydride and zirconium hydride [J].
Hayashi, T. ;
Tobita, K. ;
Nakamori, Y. ;
Orimo, S. .
JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 :119-121
[7]  
Kenneth Shultis J., 2011, An mcnp primer
[8]  
Koning A.J., 2014, TENDL-2014: TALYS-based evaluated nuclear data library
[9]  
Krishna Gopal., 2013, International Journal of Metallurgical Materials Science and Engineering (IJMMSE), V3, P41
[10]  
Lamarsh J.R., 2001, Introduction to Nuclear Engineering, V3rd