Investigation of $\rm {}^{58}Ni ( n, p ){}^{58}Co$ reaction cross-section with covariance analysis

A. Hingu, Surjit Mukherjee, S. Parashari, S. Arora, A. Gandhi, Mahima Upadhyay, Mahesh Choudhary, Sumit Bamal, N. Singh, G. Mishra, S. De, Saurav Sood, Sajin Prasad, G. Saxena, Ajay Kumar, R. Thomas, B. K. Agrawal, Karel Katovsky, A. Kumar
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Abstract

The excitation function of the $\rm {}^{58}Ni ( n, p ){}^{58}Co$ reaction is measured by using the well-established neutron activation technique and $\gamma$-ray spectroscopy. Neutrons in the energy range of 1.7 to 2.7 $\rm MeV$ were generated using the $\rm ^{7}Li(p, n)$ reaction. The neutron flux was measured by using the standard $\rm {}^{115}In ( n, n^{'} ){}^{115m}In$ monitor reaction. The results of neutron spectrum averaged cross-section of $\rm {}^{58}Ni ( n, p ){}^{58}Co$ reactions are compared with existing cross-section data available in the EXFOR data library as well as with various evaluated data libraries like ENDF/B-VIII.0, JEFF-3.3, JENDL-4.0 and CENDL-3.2. Theoretical calculations were performed using the nuclear reaction code TALYS. Various nuclear level density (NLD) models were tested and compared with the present findings. Realistic NLDs are also obtained through the spectral distribution method (SDM). The cross-section results are reported along with the absolute errors by investigating uncertainty propagation, using the covariance technique. The corrections for $\gamma$-ray true coincidence summing, low-energy background neutrons and $\gamma$-ray self attenuation are performed. The experimental cross-section obtained in the present study is consistent with previously published experimental data, evaluated libraries and theoretical calculations carried out using the TALYS code.
用协方差分析法研究 $\rm {}^{58}Ni ( n, p ){}^{58}Co$ 反应截面
利用成熟的中子活化技术和伽马射线光谱法测量了 $\rm {}^{58}Ni ( n, p ){}^{58}Co$ 反应的激发函数。能量范围在 1.7 到 2.7 $\rm MeV$ 的中子是通过 $\rm ^{7}Li(p, n)$ 反应产生的。中子通量是通过标准的 $\rm {}^{115}In ( n, n^{'} ){}^{115m}In$ 监控反应测量的。$\rm {}^{58}Ni ( n, p ){}^{58}Co$ 反应的中子谱平均截面结果与 EXFOR 数据库中的现有截面数据以及各种评估数据库(如 ENDF/B-VIII.0、JEFF-3.3、JENDL-4.0 和 CENDL-3.2)进行了比较。理论计算使用核反应代码 TALYS 进行。对各种核级密度(NLD)模型进行了测试,并与目前的研究结果进行了比较。此外,还通过频谱分布法(SDM)获得了真实的核级密度。通过使用协方差技术研究不确定性传播,报告了截面结果和绝对误差。对伽马射线真实重合和、低能背景中子和伽马射线自衰减进行了校正。本研究获得的实验截面与之前公布的实验数据、评估库和使用 TALYS 代码进行的理论计算一致。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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