水泥基碳化硼材料对裂变中子屏蔽性能的模拟
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- 英文论文题名：Simulation of neutron shielding performance of boron carbide incorporated with ordinary cement material
- 论文作者：左应红 ; 谢红刚 ; 朱金辉 ; 牛胜利
- 英文论文作者：ZUO Ying-hong ; XIE Hong-gang ; ZHU Jin-hui ; NIU Sheng-li ; Northwest Institute of Nuclear Technology
- 年：2015
- 作者机构：西北核技术研究所;
- 论文关键词：水泥 ; 碳化硼 ; 中子屏蔽 ; 蒙特卡罗模拟
- 英文论文关键词：cement ; boron carbide ; neutron shielding ; Monte Carlo simulation
- 会议召开时间：2015-09-21
- 会议录名称：中国核科学技术进展报告（第四卷）——中国核学会2015年学术年会论文集第5册（核材料分卷、辐射防护分卷）
- 语种：中文
- 分类号：TL7;TQ172.1
- 学会代码：EGVD
- 会议名称：中国核学会2015年学术年会
- 会议地点：中国四川绵阳
- 主办单位：中国核学会
- 学会名称：中国核学会
- 页数：6
- 文件大小：550k
- 原文格式：O
- 会议级别：全国
摘要
水泥作为一种核工程中常用的中子屏蔽材料,在核辐射防护中有十分重要的地位。普通水泥中掺杂不同质量比重的碳化硼,其对中子的屏蔽性能会发生变化。为研究掺杂不同比重碳化硼的水泥基屏蔽材料对中子屏蔽性能的影响,本文采用蒙特卡罗模拟方法,计算了普通水泥及普通水泥中掺杂5%、10%及20%碳化硼对不同能量中子的屏蔽性能,给出了不同厚度屏蔽材料对中子屏蔽性能的影响规律,所模拟的单能中子能量范围为0.1~10 MeV,涵盖了低能中子区及高能中子区。针对工程实际中核材料裂变中子进行屏蔽及防护也是一个重要课题,本文最后对水泥基碳化硼材料屏蔽~(235)U裂变释放的中子源进行了计算。研究结果表明,普通水泥中掺杂不同比重碳化硼,会显著影响中子的透射系数,进而改变水泥对中子的屏蔽性能;在低能中子及高能中子区,普通水泥中增加同样的碳化硼含量,对中子屏蔽效果的改善程度并不一样,表现出对低能中子的屏蔽效果优于对高能中子的屏蔽效果的特点;屏蔽体材料的厚度也是一个影响中子屏蔽性能的重要参量,欲达到同样的屏蔽效果,在普通水泥中添加碳化硼,可以有效地降低屏蔽材料的厚度,且添加的碳化硼比重越高,所需屏蔽厚度越小。
Cement is the most frequently used material for neutron shielding in nuclear engineering;it plays an important role in nuclear radiation protection.Incorporating boron carbide with different proportion into cement material will change the neutron shielding performance.To investigate the influence of admixed proportion of boron carbide on neutron shielding performance of cement based boron carbide material,the neutron shielding performance of ordinary cement and cemented based boron carbide with different thickness was numerically simulated by adopting Monte Carlo method.In the simulation,proportion of boron carbide was chosen to be 5% to 20%,and neutron energy was set with various values ranging from 0.1 keV to 10 MeV which includes low and high energy regions of neutron.It is an important issue that shield and protection of the neutron source released from nuclear materials such as uranium and plutonium in engineering practice;the shielding performance of cement based boron carbide on neutron source released from uranium 235 was calculated.The results show that incorporating boron carbide into ordinary cement will significantly affect the transmitted coefficient of neutron,and then it leads to a change of neutron shielding performance;the improvement degree is different for low energy and high energy neutron regions when incorporating a same proportion of boron carbide into cement,the shielding performance is better for low energy neutron than that for high energy neutron.The thickness of cement based boron carbide is smaller than ordinary cement,the higher the proportion of incorporated boron carbide,the smaller the thickness required.
Cement is the most frequently used material for neutron shielding in nuclear engineering;it plays an important role in nuclear radiation protection.Incorporating boron carbide with different proportion into cement material will change the neutron shielding performance.To investigate the influence of admixed proportion of boron carbide on neutron shielding performance of cement based boron carbide material,the neutron shielding performance of ordinary cement and cemented based boron carbide with different thickness was numerically simulated by adopting Monte Carlo method.In the simulation,proportion of boron carbide was chosen to be 5% to 20%,and neutron energy was set with various values ranging from 0.1 keV to 10 MeV which includes low and high energy regions of neutron.It is an important issue that shield and protection of the neutron source released from nuclear materials such as uranium and plutonium in engineering practice;the shielding performance of cement based boron carbide on neutron source released from uranium 235 was calculated.The results show that incorporating boron carbide into ordinary cement will significantly affect the transmitted coefficient of neutron,and then it leads to a change of neutron shielding performance;the improvement degree is different for low energy and high energy neutron regions when incorporating a same proportion of boron carbide into cement,the shielding performance is better for low energy neutron than that for high energy neutron.The thickness of cement based boron carbide is smaller than ordinary cement,the higher the proportion of incorporated boron carbide,the smaller the thickness required.
引文
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[2]陈飞达,汤晓斌,王鹏,等.基于蒙特卡罗方法的中子屏蔽材料设计[J].强激光与粒子束,2012,24(12):3006-3010.
[3]李文茜,李红,谢锋,等.高温堆乏燃料贮罐中子屏蔽性能计算[J].强激光与粒子束,2013,25(1):227-232.
[4]吴洋,窦海峰,唐彬,等.小型中子源高能中子照相装置准直屏蔽系统设计[J].核动力工程,2013,34(4):149-152.
[5]钱建复,沈庭云.核辐射剂量学[M].北京:国防工业出版社,2009.
[6]徐军,康青,沈志强,等.核防护用水泥基中子屏蔽材料的研究进展[J].材料开发与应用,2011,26(5):92-100.
[7]戴春娟,刘希琴,刘子利,等.铝基碳化硼材料对中子屏蔽性能的蒙特卡罗模拟[J].物理学报,2013,62(15):152801.
[8]黄益平,冯惠生,梁璐,等.含碳化硼的吸收和屏蔽中子辐射涂料的研究[J].天津大学学报,2011,44(7):639-644.
[9]许淑艳,刘保杰.核技术应用研究中的蒙特卡罗计算问题[J].核技术,2007,30(7):597-600.
[10]田东风,孙伟力.中子核反应激发函数[M].北京:国防工业出版社,2006.
[11]Chen Y J,Jia M,Tao X,et al.Calculation of prompt fission neutron spectra for~(235)U(n,f)[J].Chinese Physics C,2012,36(4):322-328.