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首页> 外文期刊>Radiation Physics and Chemistry >Optimization of an Am-Be neutron source shield design by advanced materials using MCNP code
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Optimization of an Am-Be neutron source shield design by advanced materials using MCNP code

机译：使用MCNP代码的高级材料优化AM-BE中子源屏蔽设计

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摘要

Nowadays, neutron sources are employing widely in many research as well as industrial and medical applications. A suitable neutron source with reasonable intensity, dimensions and weight is required in these applications. Am-Be is considered as an important and most famous neutron source,provides adequate neutron intensity for research and industrial applications. Typical shield materials of this source consist of some conventional and well known moderators as well as neutron and gamma absorbers. In many designs, a combined multi-layer configuration of these materials is required for better shielding efficiency which leads to a massive large shield design. Consequently, someone usually considers an Am-Be neutron source as a fixed one. However; some advantages are attributed to a portable neutron source in industriall applications. Some high-tech advanced materials have been proposed to reduce the weight and dimensions of shield design. These advance materials are much lighter and enhance shielding properties in a great extent. For example in neutron absorber advanced materials hydrogen and/or carbon content has been increased drastically leads to superior slowing down capability of these advanced materials in comparison to conventional competitors. The main objective of this work is dedicated to optimization of weight and dimensions in conventional( 241)Am-Be shield design using some state of the arts advanced materials. MCNP Monte Carlo code was employed for this purpose and equivalent neutron and gamma dose rates were calculated. The results showed that the use of advanced materials has a significant effect on total dose rate reduction. "Magnesium Borohydride" and "Kennertium" materials have the best performance in neutron and gamma dose reduction, respectively. The combination of these two materials can reduce the total dose rate in to one third of the reference value. Finally, two alternative shield designs were proposed. The first one is based on the combination of "Magnesium Borohydride" and "Kennertium", for neutron and gamma absorption. The results showed that the volume and weight in the first case are reduced by 60% and 27%, respectively. In the second case the Kennertium was replaced by "Polyethylene-78.5% Bismuth" alloy to obtain much lighter shield design. The volume and weight in the second case were reduced by 49% and 67%, respectively.
机译：如今，中子源在许多研究中广泛使用以及工业和医疗应用。在这些应用中需要具有合理强度，尺寸和重量的合适中子源。 am-be被认为是一个重要而最着名的中子源，为研究和工业应用提供了足够的中子强度。该源的典型盾构材料由一些常规和公知的中间剂以及中子和伽马吸收剂组成。在许多设计中，需要具有更好的屏蔽效率的这些材料的组合多层配置，从而导致大量的大屏蔽设计。因此，某人通常认为AM-中子源作为固定的。然而;一些优点归因于工业应用中的便携式中子源。已经提出了一些高科技先进材料来减少屏蔽设计的重量和尺寸。这些提前材料在很大程度上更轻，提高屏蔽性能。例如，在中子吸收剂先进的材料中，氢气和/或碳含量随着与传统竞争对手相比，这些先进材料的卓越速度越来越慢地导致卓越的放缓。这项工作的主要目的是使用某些技术先进材料的常规（241）AM-Be Shield设计优化重量和尺寸。 MCNP Monte Carlo代码用于此目的，并计算等同的中子和γ剂量率。结果表明，使用先进材料对总剂量率降低具有显着影响。 “硼氢化镁”和“kennertium”材料分别具有中子和γ剂量减少的最佳性能。这两种材料的组合可以将总剂量率降低到参考值的三分之一。最后，提出了两种替代屏蔽设计。第一个基于“硼氢化氢”和“kennertium”的组合，用于中子和γ吸收。结果表明，第一案例中的体积和重量分别降低了60％和27％。在第二种情况下，Kennertium被“聚乙烯-78.5％铋”合金所取代，以获得更轻的盾构设计。第二种情况下的体积和重量分别降低了49％和67％。

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