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中国物理学会期刊

硼氢化物的热中子散射机理

CSTR: 32037.14.aps.75.20251314

Investigation of thermal neutron scattering mechanisms in borohydrides

CSTR: 32037.14.aps.75.20251314
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  • 硼氢化物(X\mathrmBH_4, X=\mathrmLi,\;Na,\;K)具有“元素协同”(硼吸收截面高、氢的慢化能力好)效应, 可以视为良好的中子屏蔽材料. 但是, 目前国际评价数据库中缺少硼氢化物实验和评价热散射数据, 不利于该材料的屏蔽和慢化性能评估. 本文基于密度泛函的第一性原理计算了晶格参数、电子结构和声子态密度等材料性质, 并研制了相应的S(\textα,\textβ)数据和热中子散射截面. 模拟得到的晶格参数与实验符合较好, 对比了X\mathrmBH_4的电子结构和声子态密度, 给出了硼氢化物中阳离子X, B, H对应的相干弹性散射截面、非相干弹性散射截面和非弹性散射截面, 结果表明, 由于阳离子X的不同, 硼氢化物X\mathrmBH_4中各核素的热中子截面存在明显差异. 为评估硼氢化物热散射数据对中子屏蔽效应的影响, 本文采用简化聚变源模型, 使用OpenMC程序对比了不同物理模型下的泄漏中子能谱. 结果显示, 自由气体模型(FGM)由于忽略了晶格束缚效应, 对中子的慢化能力描述不准确, 此外, 由于氢元素较大的非相干散射截面, 各核素相干弹性散射截面对中子能谱的影响较小. 本文的研究结果填补了硼氢化物热中子截面数据的缺失, 为进一步研究硼氢化物作为中子屏蔽材料的应用奠定了基础. 本文数据集可在科学数据银行数据库https://www.doi.org/10.57760/sciencedb.j00213.00219中访问.

     

    Borohydrides (X\mathrmBH_4, X\mathrm=Li,\; Na,\; K) exhibit an “elemental synergy” effect, characterized by the high neutron absorption cross-section of boron and the excellent moderation capability of hydrogen, making them promising candidates for neutron shielding materials. However, the current lack of experimental and evaluated thermal scattering data for borohydrides in international nuclear data libraries hinders the accurate assessment of their shielding and moderation performance. In this study, material properties including lattice parameters, electronic structures, and phonon densities of states are calculated based on first-principles density functional theory. Subsequently, the corresponding S(\alpha, \beta) data and thermal neutron scattering cross-sections are developed. The simulated lattice parameters show good agreement with the experimental data. By comparing the electronic structures and phonon densities of states of X\mathrmBH_4, the coherent elastic, incoherent elastic, and inelastic scattering cross-sections for the cations X, B, and H are obtained. The results indicate that the thermal neutron cross-sections of the constituent nuclides in \mathrmXBH_4 exhibit significant differences depending on the cation X. To evaluate the impact of thermal scattering data on neutron shielding effects, a simplified fusion source model is employed using the OpenMC code to compare the leaked neutron energy spectra under different physical models. The results demonstrate that the Free Gas Model (FGM) provides an inaccurate description of neutron moderation due to its neglect of lattice binding effects. Furthermore, owing to the large incoherent scattering cross-section of hydrogen, the coherent elastic scattering cross-sections of the various nuclides have a negligible impact on the neutron energy spectrum. This research fills the gap in thermal neutron cross-section data for borohydrides and lays a foundation for further investigations into their application as neutron shielding materials. The datasets presented in this paper, including the ScienceDB, are openly available at https://www.doi.org/10.57760/sciencedb.j00213.00219.

     

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