The reaction cross sections of \(^{197}\)Au(n,2n)\(^{196}\)Au, \(^{115}\)In(n,n\(^{\prime })^{115m}\)In, \(^{232}\)Th(n,f)\(^{97}\)Zr, and \(^{238}\)U(n,f)\(^{97}\)Zr reactions were measured at different neutron energies using standard neutron activation analysis (NAA) technique followed by off-line \(\gamma \)-ray spectrometry. The irradiation was performed using the BARC-TIFR Pelletron facility in Mumbai, India. The quasi-monoenergetic neutron beam was generated using the \(^7\)Li(p,n)\(^7\)Be reaction. The measured data are compared with available experimental data in the EXFOR database, different evaluated libraries such as ENDF/B-VIII.0, JEFF-3.3, JENDL-4.0, CENDL-3.1, IRDFF II, TENDL-2017 and with the results predicted using nuclear modular code TALYS-1.9. The TALYS-1.9 code was used for a better description of the present work and literature data. The reactions studied in the present paper are considered flux monitor reactions as they are widely used for the measurement of neutron flux in NAA-technique.

\(^{197}\) Au(n,2n) \(^{196}\) Au, \(^{115}\) In(n,n \(^{\prime })的反应截面^{115m}\)在, \(^{232}\) Th(n,f) \(^{97}\) Zr, 和\(^{238}\) U(n,f) \(^ {97}\) Zr 反应在不同的中子能量下使用标准中子活化分析 (NAA) 技术和离线\(\gamma \)射线光谱法测量。辐照是使用位于印度孟买的 BARC-TIFR Pelletron 设施进行的。准单能中子束是使用\(^7\) Li(p,n) \(^7\) 产生的是反应。将测量数据与 EXFOR 数据库、不同评估库（如 ENDF/B-VIII.0、JEFF-3.3、JENDL-4.0、CENDL-3.1、IRDFF II、TENDL-2017）中的可用实验数据进行比较，并预测结果使用核模块代码 TALYS-1.9。TALYS-1.9 代码用于更好地描述当前的工作和文献数据。本文中研究的反应被认为是通量监测反应，因为它们被广泛用于 NAA 技术中的中子通量测量。