中子能量为14.96±0.03 MeV的121,123Sb同位素中子诱导反应截面分析

IF 2.1 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Applied Radiation and Isotopes Pub Date : 2025-06-01 Epub Date: 2025-02-28 DOI:10.1016/j.apradiso.2025.111758
Shivani Sharma , Vandana , Pargin Bangotra , N.L. Singh , Mayur Mehta , R.K. Singh , R.J. Makwana , Mitul Abhangi , Ratnesh Kumar , Himanshu Sharma , Sudhirsinh Vala , K. Katovsky
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引用次数: 0

摘要

锑(Sb)的截面测量对于改变或停滞核反应堆中的中子通量速率至关重要。根据EXFOR的报道,Sb同位素的中子诱导反应截面数据很少。对121Sb和123Sb在单能中子能量为14.96±0.03 MeV时的反应截面进行了全面的分析。实验是在印度古吉拉特邦等离子体研究所中子和离子辐照设施进行的。利用中子活化技术对27Al(n,α)24Na反应进行了通量监测,并对(n,2n)、(n,p)反应的截面进行了估算。用D-T聚变反应产生的单能中子轰击Sb的天然样品,产生放射性。采用基于GENIE软件的高纯锗探测器(HPGe),分辨率为2.1 keV, γ射线能量为60Co的1.33 MeV,对发射的伽马光峰进行计数。计算结果与EXFOR已有的研究结果进行了比较。通过采用不同的输入参数,以及最新的评估核数据库(ENDF/B-VIII),使用TALYS-2.0统计代码估计截面值。0,杰夫- 3.3)。为了获得更精确的数据,利用各参数之间的相关系数来传播各参数的不确定性。这种系统详细的协方差分析有助于减少目前的差异和改进核数据。
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Analysis of neutron induced reaction cross-section on 121,123Sb isotopes at neutron energy of 14.96 ± 0.03 MeV
The cross-section measurement of Antimony (Sb) is pivotal to modify or stagnate the rate of neutron flux in nuclear reactors. Neutron induced reaction cross-section data for isotopes of Sb is meagre as per reported in EXFOR. A comprehensive attempt has been made to analyse the reaction cross-section of 121Sb and 123Sb at monoenergetic neutron energy of 14.96 ± 0.03 MeV. The experiment was performed at the Neutron and Ion Irradiation Facility, Institute for Plasma Research (IPR), Gujarat (India). The 27Al(n,α)24Na reaction is used to monitor the flux and to estimate the cross-section of (n,2n), (n,p) reactions using neutron activation technique. Monoenergetic neutrons generated by D-T fusion reaction were bombarded on the natural sample of Sb to induce radioactivity. A High Purity Germanium detector (HPGe) with a resolution of 2.1 keV at 1.33 MeV γ-ray energy of 60Co based on GENIE software was used for the counting of emitted gamma photo peaks. Calculated results are compared with the existing studies from EXFOR. The cross-section values are estimated using TALYS-2.0 statistical code by employing different input parameters, along with the latest Evaluated Nuclear data libraries (ENDF/B-VIII.0, JEFF-3.3). To obtain more precise data, uncertainties from various parameters are propagated using the correlation coefficients among all the parameters. This systematic detailed covariance analysis helps to reduce the present discrepancies and to refine the nuclear data.
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来源期刊
Applied Radiation and Isotopes
Applied Radiation and Isotopes 工程技术-核科学技术
CiteScore
3.00
自引率
12.50%
发文量
406
审稿时长
13.5 months
期刊介绍: Applied Radiation and Isotopes provides a high quality medium for the publication of substantial, original and scientific and technological papers on the development and peaceful application of nuclear, radiation and radionuclide techniques in chemistry, physics, biochemistry, biology, medicine, security, engineering and in the earth, planetary and environmental sciences, all including dosimetry. Nuclear techniques are defined in the broadest sense and both experimental and theoretical papers are welcome. They include the development and use of α- and β-particles, X-rays and γ-rays, neutrons and other nuclear particles and radiations from all sources, including radionuclides, synchrotron sources, cyclotrons and reactors and from the natural environment. The journal aims to publish papers with significance to an international audience, containing substantial novelty and scientific impact. The Editors reserve the rights to reject, with or without external review, papers that do not meet these criteria. Papers dealing with radiation processing, i.e., where radiation is used to bring about a biological, chemical or physical change in a material, should be directed to our sister journal Radiation Physics and Chemistry.
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