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测量锌、锆、锑和锑在1至2兆电子伏能量范围内的快中子诱发(n,γ)反应截面。

Measurement of fast neutron induced (n,γ) reaction cross-section of Zn, Zr, Sb and Sb in the energy range of 1 to 2 MeV.

作者信息

Tawade N S, Kumar S, Patra S, Tripathi R, Datrik C S, Pujari P K, Thomas R G, Mishra G, Kumar A, De S, Kumawat H

机构信息

Homi Bhabha National Institute, Anushaktinagar, Mumbai, 400094, India; Radiochemistry Division, Bhabha Atomic Research Centre, Mumbai, 400085, India.

Radiochemistry Division, Bhabha Atomic Research Centre, Mumbai, 400085, India.

出版信息

Appl Radiat Isot. 2024 Dec;214:111535. doi: 10.1016/j.apradiso.2024.111535. Epub 2024 Sep 28.

DOI:10.1016/j.apradiso.2024.111535
PMID:39357256
Abstract

The (n,γ) reaction cross-section for the elements Zn, Zr, Sb and Sb, present in the reactor structural/shielding materials, was measured by neutron activation technique in the neutron energy region of 1-2 MeV as very limited data is available in this energy range. Further, the neutron spectrum peaks in this energy region for the fast breeder reactors and proposed accelerator driven sub-critical systems. The natural strontium (Sr) element was used as a neutron flux monitor by considering effective combined reaction cross-section for Sr(n,γ)Sr and Sr(n,n')Sr reactions. The pellets of mixture of sample and monitor were irradiated by a quasi-mono energetic fast neutron beam, generated by Li(p,n)Be reaction at FOTIA, Bhabha Atomic Research Centre, Mumbai, India. The activity of activation products was measured by off-line gamma-ray spectrometry using High Purity Germanium Detector (HPGe). The present data with improved uncertainty and covariance analysis enhance the cross-section data base for better constraining the evaluated data and theoretical models. The theoretical (n,γ) reaction cross-sections were calculated using TALYS 1.96, which could reasonably explain the present data with the Fermi gas level density prescription.

摘要

利用中子活化技术,在1 - 2兆电子伏的中子能量区域内,测量了反应堆结构/屏蔽材料中存在的锌(Zn)、锆(Zr)、锑(Sb)和锑元素的(n,γ)反应截面,因为该能量范围内可获得的数据非常有限。此外,快中子增殖反应堆和拟议的加速器驱动次临界系统的中子能谱在该能量区域出现峰值。通过考虑锶(Sr)(n,γ)Sr和Sr(n,n')Sr反应的有效组合反应截面,将天然锶(Sr)元素用作中子通量监测器。样品和监测器混合物的颗粒由印度孟买巴巴原子研究中心FOTIA的Li(p,n)Be反应产生的准单能快中子束辐照。使用高纯锗探测器(HPGe)通过离线γ射线能谱法测量活化产物的活度。具有改进的不确定度和协方差分析的当前数据增强了截面数据库,以便更好地约束评估数据和理论模型。使用TALYS 1.96计算理论(n,γ)反应截面,其可以使用费米气体能级密度公式合理地解释当前数据。

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