铝、锆、铟和金上快中子诱导反应的激发函数

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
B. Liu , G. Tian , R. Han , F. Shi , H. Sun , Z. Chen , Z. Zhang , Q. Li , P. Luo
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引用次数: 0

摘要

利用活化法和离线 γ 射线光谱技术介绍了 D-T 中子诱导的 27Al(n,α)24Na、96Zr(n,2n)95Zr、115In(n,p)115gCd、115In(n, 2n)114mIn 和 197Au(n,2n)196/196m2Au 反应的横截面。利用协方差分析估算了截面的不确定性传播和相关性。结果表明,我们的研究结果与 EXFOR 库中大部分以前的文献数据是一致的。实验值(包括以前的文献数据)与 CENDL-3.2、BROND-3.1、ENDF/B-VIII.0、IRDFF-II、JENDL-5 和 JEFF-3.3 库的评估核数据进行了比较。此外,还使用 TALYS-2.0 代码对这些激发函数进行了理论计算,最大中子能量为 20 MeV。结果表明,实验数据与计算结果和评估数据之间存在明显差异。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Excitation functions for fast neutron induced reactions on Al, Zr, In and Au

Cross sections of the 27Al(n,α)24Na, 96Zr(n,2n)95Zr, 115In(n,p)115gCd, 115In(n, 2n)114mIn and 197Au(n,2n)196/196m2Au reactions induced by D-T neutrons are presented with the activation method and off-line γ-ray spectrometry technique. Uncertainty propagation and correlation of the cross sections were estimated using covariance analysis. It shows that, our results are consistent with most of the previous literature data of EXFOR library. Experimental values, including previous literature data, are compared with evaluated nuclear data of the CENDL-3.2, BROND-3.1, ENDF/B-VIII.0, IRDFF-II, JENDL-5 and JEFF-3.3 libraries. Besides, these excitation functions were theoretically calculated by using the TALYS-2.0 code up to the neutron energy of 20 MeV. It shows that significant discrepancies were found between experiment data and those of calculated results and evaluated data.

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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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