Cf中子源的紧凑型屏蔽与辐照器设计
Compact shielding and irradiator design of a Cf neutron source.
作者信息
Nasrabadi Maryam, Ebrahimibasabi Ehsan, Tavakoli-Anbaran Hossein
机构信息
Faculty of Physics and Nuclear Engineering, Shahrood University of Technology, Shahrood, Iran.
Faculty of Physics and Nuclear Engineering, Shahrood University of Technology, Shahrood, Iran.
出版信息
Appl Radiat Isot. 2019 Jan;143:29-34. doi: 10.1016/j.apradiso.2018.10.005. Epub 2018 Oct 12.
New developments are under way to reduce the weight and volume of neutron shielding structures using multi-layered materials. The present study aimed at designing and simulating an appropriate neutron shielding material based on a Cf source using MCNPX code. The proposed design is composed of concentric cylinders and sphere layers with a source. The shielding matter consists of paraffin and paraffin +10% graphite as a moderator, beryllium as a reflector and multiplier and boron carbide and lead tungsten as a thermal neutron and gamma absorber, respectively. The results indicate that, compared to previously reported shielding assemblies, the volume and the weight of the proposed design could be significantly reduced by about 97% and 75%, respectively. Thermal and fast neutron fluxes in the irradiation channel were optimized to achieve maximum values for NAA, PGNAA and other applications.
目前正在进行新的研发，以使用多层材料减轻中子屏蔽结构的重量和体积。本研究旨在使用MCNPX代码，基于Cf源设计并模拟一种合适的中子屏蔽材料。所提出的设计由带有源的同心圆柱层和球层组成。屏蔽物质包括作为慢化剂的石蜡和石蜡+10%石墨、作为反射体和增殖剂的铍，以及分别作为热中子和γ射线吸收体的碳化硼和铅钨。结果表明，与先前报道的屏蔽组件相比，所提出设计的体积和重量可分别显著减少约97%和75%。对辐照通道中的热中子通量和快中子通量进行了优化，以实现中子活化分析（NAA）、脉冲快中子活化分析（PGNAA）及其他应用的最大值。
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