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采用蒙特卡罗方法, 运用MCNP4C程序研究了碳化硼含量20%–40%、中子能量200 eV–15 keV、材料厚度0.3–2 cm对B4C/Al复合材料中子屏蔽性能的影响. 结果表明: 碳化硼含量与中子透射系数呈一次线性下降关系; 同含量的碳化硼, B4C/Al材料的中子屏蔽效果要大大优于聚乙烯碳化硼材料; 在等厚度条件下, 模拟试样B20等的中子屏蔽效果要优于水、铜、混凝土等常规屏蔽材料; 材料厚度与中子透射系数呈指数下降关系, 且单位厚度的增加对中子透射系数改变很大; 含硼量对热中子透射系数影响很大; 在热中子能区, 中子每单位能量的变化对中子透射系数改变较大; 在慢中子能区, 中子每单位能量的变化对中子透射系数改变很小.Three groups of neutron shielding experiments were set up to study the shielding performance of B4C/Al composite, using the Monte-Carlo method. We have made the following changes: the content of boron carbide 20%–40%, neutron energy 200 eV–15 keV, material thickness 0.3–2 cm, so that we can draw the conclusions: the content of boron carbide and neutron transmission coefficient show a linear relation, with a big drop; under the same neutron energy, the neutron-shielding qualities of simulated specimens are for better than polyethylene boron carbide at the same content of B4C and water, copper, and concrete at the same thickness; an exponential decline relationship is exhibited by material thickness and neutron transmission coefficient, which change greatly with the increase in unit material thickness; the content of boron affects the thermal neutron transmission coefficient seriously. In the thermal neutron energy region, the change of per unit neutron energy(100 eV) has a big influence on neutron transmission coefficient. In the slow neutron energy region, the influence is small.
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Keywords:
- neutron transmission coefficient /
- Monte-Carlo method /
- aluminum matrix composite material /
- boron carbide
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[1] Cao Z W, Zhang J H 2006 liaon. Chem. Ind. 35 399 (in Chinese) [曹仲文, 张继红 2006 辽宁化工 35 399]
[2] Song Y G, Zheng J, Tan M F 2006 J. Nanj. Norm. Univ. 6 53 (in Chinese) [宋永刚, 郑晶, 谭梅风 2006 南京师范大学学报 6 53]
[3] Li G, Jian M, Wang M L, Wang G C, Liu X Z 2011 Mat. Rev. A 25 7 (in Chinese) [李刚, 简敏, 王美玲, 王贯春, 刘晓珍 2011 材料导报 A 25 7]
[4] Alizadeh M 2010 Mater. Sci. Eng. A 52 578
[5] Tuncer N, Tasdelen B, Arslan G 2011 Ceram. Int’l. 37 2861
[6] Kenneth D 2009 Nuclear engineering handbook (New York: CBC Press) p152
[7] Xu X H, Chen J 1995 Rad. Prot. 15 9 (in Chinese) [徐小桦, 陈晶 1995 辐射防护 15 9]
[8] Zhang F Q, Yang J L, Li Z H, Ying C T, Liu G J 2007 Acta Phys. Sin. 56 3577 (in Chinese) [章法强, 杨建伦, 李正宏, 应纯同, 刘广均 2007 物理学报 56 3577]
[9] Xue N, Zhao B 2007 Rad. Prot. 27 65 (in Chinese) [薛娜, 赵博 2007 辐射防护 27 65]
[10] Li D P, Pan Z Q 1987 Rad. Prot. Man. (Book 1) (BeiJing: Atomic Energy Press) p320 (in Chinese) [李德平, 潘自强 1987 辐射防护手册(第一册)(北京:原子能出版社) 第320页]
[11] Hu J D, Hu H R, Ding D H 1980 nucl. Tech. 3 44 (in Chinese) [胡建达, 胡厚仁, 丁大宏 1980 核技术 3 44]
[12] Zeng X M, Zhou P, Qin P Z, Bao M, Guo G S, Xu Z Y 2011 nucl. Tech. 34 188 (in Chinese) [曾心苗, 周鹏, 秦培中, 鲍矛, 郭广水, 许自炎 2011 核技术 34 188]
[13] Wei Q L, Wang Y, Yang B, Yang T, Liu Y B 2010 nucl. Tech. 33 367 (in Chinese) [魏强林, 王毅, 杨波, 杨婷, 刘义保 2010 核技术 33 367]
[14] Li Z F, Xue X X 2011 J. Northeastern Univ. (Natural Science) 32 1716 [李哲夫, 薛向欣 2011 东北大学学报(自然科学版) 32 1716]
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