MONTE-CARLO (MC) ANALYSIS OF BORATED MATERIALS FOR NEUTRON SHIELDING APPLICATIONS

A. Albarodi, P. Uslu Kiçeci, S. Uzun Duran, B. Demirköz
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Abstract

Neutron shielding is of utmost importance in radiation environments such as nuclear reactors and particle accelerators and in fields such as health physics. In this work, the percentages of neutrons stopped by shields comprising of boron minerals (HDPE/B2O3, Epoxy/Priceite, Epoxy/Colemanite, Epoxy/Kernite) in their composition against neutron radiation of different energies is investigated using two separate MC simulations. Different layer combinations of epoxy based borated shielding materials with HDPE sheets were then simulated to find the optimum shielding configuration. In addition, radioactivation studies were carried out for these designs. The most suitable design was found to be the layered setup of the HDPE sheet and the epoxy/colemanite composite sheet for mixed neutron energies (
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中子屏蔽用硼化材料的蒙特卡罗分析
中子屏蔽在核反应堆和粒子加速器等辐射环境以及健康物理学等领域中至关重要。在这项工作中,使用两个独立的MC模拟研究了由硼矿物(HDPE/B2O3,环氧树脂/Priceite,环氧树脂/Colemanite,环氧树脂/Kernite)组成的屏蔽物在不同能量中子辐射下阻挡中子的百分比。然后对环氧基硼化屏蔽材料与HDPE片材的不同层位组合进行了模拟,以找到最佳屏蔽结构。此外,还对这些设计进行了放射性研究。最合适的设计是HDPE片材和环氧树脂/colemanite复合片材的分层设置,用于混合中子能量(
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