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<p><strong>Measurement of <sup>100</sup>Mo (n, 2n) <sup>99</sup>Mo reaction cross section and covariance analysis using extended unscented transformation technique at the incident neutron energy of 13.9 MeV</strong></p>

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Title Statement <p><strong>Measurement of <sup>100</sup>Mo (n, 2n) <sup>99</sup>Mo reaction cross section and covariance analysis using extended unscented transformation technique at the incident neutron energy of 13.9 MeV</strong></p>
 
Added Entry - Uncontrolled Name Prasanna Ram, Sangeetha ; Department of Instrumentation, V E S Institute of Technology, Mumbai 400 074, India
Nair, Jayalekshmi
Suryanarayana, S V
Singh Dhanu, Laxman
Naik, Haladhara
Ganesan, S
 
Uncontrolled Index Term Extended unscented transformation, 100Mo (n, 2n) 99Mo activation reaction cross-section, Off-line -ray spectrometry, Covariance analysis, TALYS 1.8, ENDF-B/VIII.0
 
Summary, etc. <p>In this paper, the measurement and covariance analysis of the cross section of <sup>100</sup>Mo (n, 2n) <sup>99</sup>Mo reaction, with the <sup>197</sup>Au (n, 2n)<sup>196 </sup>Au reaction being used as the monitor, at the incident neutron energy of 13.9 MeV is reported. The <sup>3</sup>H (d, n) <sup>4</sup>He nuclear reaction is used as the neutron source. The experiment was performed at the Purnima neutron facility, BARC. <br /> The method of activation with off-line -ray spectrometry is used. The covariance analysis of the <sup>100</sup>Mo (n, 2n) <sup>99</sup>Mo reaction is also performed, for the first time, using the extended unscented transformation (EUT) technique<sup>1</sup>, which is an extension of unscented transformation (UT) technique<sup>2</sup>, for the determination of partial uncertainties arising due to attributes in combination with the micro-correlation technique of Geraldo and Smith<sup>3</sup>. The present results obtained for <sup>100</sup>Mo (n, 2n) <sup>99</sup>Mo reaction cross section are found to be in good agreement with EXFOR data and the theoretically calculated value using the TALYS 1. 8 code. Comparisons with the data in the available basic evaluated nuclear data libraries, such as ENDF/B-VIII.0, JEFF-3.3, JENDL-4.0, ROSFOND-2010, CENDL-3.1 and TENDL 2017 are also presented and discussed.</p>
 
Publication, Distribution, Etc. Indian Journal of Pure & Applied Physics (IJPAP)
2022-10-20 10:39:34
 
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http://op.niscair.res.in/index.php/IJPAP/article/view/67671
 
Data Source Entry Indian Journal of Pure & Applied Physics (IJPAP); ##issue.vol## 58, ##issue.no## 5 (2020): Indian Journal of Pure & Applied Physics
 
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