Suppr超能文献

γ相铀和铀的热中子散射截面。

Thermal neutron scattering cross sections of U and U in the γ phase.

作者信息

Saltos Andrea A, Peters Nickie J, Hammond Karl D

机构信息

Nuclear Engineering Program, University of Missouri, Columbia, MO 65211, United States of America.

出版信息

J Phys Condens Matter. 2018 Oct 17;30(41):415401. doi: 10.1088/1361-648X/aadbc8. Epub 2018 Aug 21.

Abstract

The development of metallic, low-enrichment uranium fuels requires accurate prediction of their neutron transport properties and reactivity parameters, which in turn require thermal neutron scattering data. Accurate prediction of thermal neutron scattering data, including thermal cross sections, requires knowledge of the phonon scattering properties of the medium, but such matrix binding effects in next-generation fuels such as U-Mo, U-Zr, and U-Si are typically neglected because these effects are often difficult to measure or calculate. Using molecular dynamics simulations with previously published interatomic potentials, we calculate the phonon dispersion relations and phonon densities of states for U and U in the α and γ phases. The performance of these potentials was evaluated using published ab initio simulation data and inelastic neutron scattering data. The phonon densities of states obtained by each potential were then utilized to calculate the thermal neutron scattering cross sections of U and U at 1113 K using the NJOY program. The resulting thermal neutron scattering cross sections are assessed by comparison to data obtained from available experimental densities of states. The cross sections generated show how the addition of binding effects decreases the cross section by up to a factor of six over the free-atom model. A definite effect on reactivity is also demonstrated by the use of these thermal libraries on a simple core model. As a consequence, the cross sections generated in this work provide a better description of the true cross section than the free-atom data currently available. We also discuss the sensitivity of the thermal scattering cross sections to the phonon density of states.

摘要

金属低浓铀燃料的研发需要精确预测其中子输运特性和反应性参数,而这又需要热中子散射数据。准确预测热中子散射数据,包括热截面,需要了解介质的声子散射特性,但在U-Mo、U-Zr和U-Si等下一代燃料中,这种基体结合效应通常被忽略,因为这些效应往往难以测量或计算。利用分子动力学模拟和先前发表的原子间势,我们计算了α相和γ相U和U的声子色散关系和声子态密度。使用已发表的从头算模拟数据和非弹性中子散射数据评估了这些势的性能。然后利用每个势得到的声子态密度,使用NJOY程序计算了1113 K下U和U的热中子散射截面。通过与从可用的实验态密度获得的数据进行比较,对所得的热中子散射截面进行了评估。生成的截面表明,与自由原子模型相比,结合效应的加入如何使截面降低了高达六倍。在一个简单的堆芯模型上使用这些热库也证明了对反应性有明确的影响。因此,与目前可用的自由原子数据相比,这项工作中生成的截面能更好地描述真实截面。我们还讨论了热散射截面对声子态密度的敏感性。

文献检索

告别复杂PubMed语法,用中文像聊天一样搜索,搜遍4000万医学文献。AI智能推荐,让科研检索更轻松。

立即免费搜索

文件翻译

保留排版,准确专业,支持PDF/Word/PPT等文件格式,支持 12+语言互译。

免费翻译文档

深度研究

AI帮你快速写综述,25分钟生成高质量综述,智能提取关键信息,辅助科研写作。

立即免费体验