  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.
