Abstract
In this work, we investigated fission cross-section and fission yield curves of 238U for neutron-induced fission reaction process at 1.7 MeV and 14.3 MeV for five different fission fragment models and three yield models. For this reason, we calculated the fission cross-section curves and independent yield \documentclass[12pt]{minimal} \usepackage{amsmath} \usepackage{wasysym} \usepackage{amsfonts} \usepackage{amssymb} \usepackage{amsbsy} \usepackage{mathrsfs} \usepackage{upgreek} \setlength{\oddsidemargin}{-69pt} \begin{document}$$\:{Y}_{I}\left(A\right)$$\end{document} and primary fission fragment yield \documentclass[12pt]{minimal} \usepackage{amsmath} \usepackage{wasysym} \usepackage{amsfonts} \usepackage{amssymb} \usepackage{amsbsy} \usepackage{mathrsfs} \usepackage{upgreek} \setlength{\oddsidemargin}{-69pt} \begin{document}$$\:Y\left(A\right)$$\end{document} for 238U(n, f) reaction based on the theoretical models. The obtained model results were compared with experimental data in the literature and recommended suitable models for both cross-section and yield calculations. Moreover, neutron emission multiplicity distribution \documentclass[12pt]{minimal} \usepackage{amsmath} \usepackage{wasysym} \usepackage{amsfonts} \usepackage{amssymb} \usepackage{amsbsy} \usepackage{mathrsfs} \usepackage{upgreek} \setlength{\oddsidemargin}{-69pt} \begin{document}$$\:P\left({\upnu\:}\right)$$\end{document}, the mass-dependent and the energy-dependent average neutron multiplicities, \documentclass[12pt]{minimal} \usepackage{amsmath} \usepackage{wasysym} \usepackage{amsfonts} \usepackage{amssymb} \usepackage{amsbsy} \usepackage{mathrsfs} \usepackage{upgreek} \setlength{\oddsidemargin}{-69pt} \begin{document}$$\:\stackrel{-}{\nu\:}\left(A\right)$$\end{document} and \documentclass[12pt]{minimal} \usepackage{amsmath} \usepackage{wasysym} \usepackage{amsfonts} \usepackage{amssymb} \usepackage{amsbsy} \usepackage{mathrsfs} \usepackage{upgreek} \setlength{\oddsidemargin}{-69pt} \begin{document}$$\:\stackrel{-}{\nu\:}\left(E\right)$$\end{document} were calculated and discussed to provide new data to the literature.
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Kapsamı
Uluslararası
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Type
Hakemli
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Index info
WOS.SCI
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Language
English
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Article Type
None
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Keywords
Fission reaction Fission yield Fission cross-section Neutron-induced reaction