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Study of neutron multiplicity in ²³²Th (n,f) reaction using TALYS-1.96
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Study of neutron multiplicity in ²³²Th (n,f) reaction using TALYS-1.96
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The nuclear scientific community views $^{232}$Th as an option for fuel in the future nuclear energy program. Numerous experimental studies have been conducted to determine the cross-section; however, very few have been performed to calculate the total neutron multiplicity above 10 MeV energy. In this work, we have compared the experimental data of average neutron multiplicity at different incident energies from EXFOR with the evaluated data from ENDF/B-VI, JENDL-4.0, and the calculated data from TALYS-1.96. The experimental data are in good agreement with the evaluated data from both the ENDF/B-VI and JENDL-4.0 libraries and at high incident energy (7 MeV), the TALYS-1.96 data are also in agreement with the experimental data.
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