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<p>In this work, we investigated fission cross-section and fission yield curves of <sup>238</sup>U for neutron-induced fission reaction process at 1.7&#xa0;MeV and 14.3&#xa0;MeV for five different fission fragment models and three yield models. For this reason, we calculated the fission cross-section curves and independent yield <InlineEquation ID="IEq1"> <EquationSource Format="TEX">\(\:{Y}_{I}\left(A\right)\)</EquationSource> </InlineEquation> and primary fission fragment yield <InlineEquation ID="IEq2"> <EquationSource Format="TEX">\(\:Y\left(A\right)\)</EquationSource> </InlineEquation> for <sup>238</sup>U(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 <InlineEquation ID="IEq3"> <EquationSource Format="TEX">\(\:P\left({\upnu\:}\right)\)</EquationSource> </InlineEquation>, the mass-dependent and the energy-dependent average neutron multiplicities, <InlineEquation ID="IEq4"> <EquationSource Format="TEX">\(\:\stackrel{-}{\nu\:}\left(A\right)\)</EquationSource> </InlineEquation> and <InlineEquation ID="IEq5"> <EquationSource Format="TEX">\(\:\stackrel{-}{\nu\:}\left(E\right)\)</EquationSource> </InlineEquation> were calculated and discussed to provide new data to the literature.</p>

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Investigation of Fission Yield and Fission Cross-Section of 238U(n, f) in 1.7 MeV and 14.3 MeV

  • 期刊论文

  • 发表日期：

    2025年11月7日

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  • Ozan Artun

摘要

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 \(\:{Y}_{I}\left(A\right)\) and primary fission fragment yield \(\:Y\left(A\right)\) 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 \(\:P\left({\upnu\:}\right)\) , the mass-dependent and the energy-dependent average neutron multiplicities, \(\:\stackrel{-}{\nu\:}\left(A\right)\) and \(\:\stackrel{-}{\nu\:}\left(E\right)\) were calculated and discussed to provide new data to the literature.