核反应堆生物屏蔽用碳化硼添加剂提高沸石和方铅矿的中子屏蔽能力

R. Mehrnejad
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引用次数: 1

摘要

核反应堆的生物屏蔽是一个重要的研究方向,降低这些设施的复杂性和成本是一个重要的研究方向。本文采用钛沸石、方铅矿和碳化硼作为核反应堆的屏蔽靶。在混凝土配合比设计中采用了世界上许多地方都存在的Datolite和方铅矿矿物。碳化硼是中子吸收过程的重要材料。物质俘获和中子俘获截面是解释样品中子屏蔽特性的有效原因。用14.1 MeV反应堆中子源对样品进行了中子截面模拟。利用Geant4蒙特卡罗程序估计了每个样品的截面和捕获中子数。结果表明,增大碳化硼浓度可提高Datolite和方铅矿的截面值。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Improving Neutron Shielding Capacities of Datolite and Galena by Boron Carbide Additive for Nuclear Reactor Biological Shielding
Biological shielding of nuclear reactor is an important interest and diminishing the intricacy and cost of theseinstallations is important interest. In this paper, we used Datolite and Galena minerals and boron carbide for nuclear reactor shielding aim. Datolite and Galena minerals that exist in many parts of world were used in the concrete mix design. Boron carbide is an important material for neutron absorption processes. The cross section in matter and neutron capture is utilizable causes to explain neutron shielding characteristics of samples. Neutron cross section simulations of samples have done by using a source of 14.1 MeV reactor neutrons. Cross section and number of captured neutrons of each sample were estimated by using Geant4 Monte Carlo code. As a result, growing boron carbide concentration can raise cross section value of Datolite and galena.
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