  The neutron-induced fission cross sections were simultaneously evaluated for
the JENDL-5 library for $^{233,235}$U and $^{239,241}$Pu from 10 keV to 200 MeV
and for $^{238}$U and $^{240}$Pu from 100 keV to 200 MeV. Evaluation was
performed by least-squares fitting of Schmittroth's roof function to the
logarithms of the experimental cross sections and cross section ratios in the
EXFOR library. A simultaneous evaluation code SOK was used with its extension
to data in arbitrary unit. The outputs of the code were adopted as the
evaluated cross sections without any further corrections. The newly obtained
evaluated cross sections were compared with the evaluated cross sections in the
JENDL-4.0 library and the IAEA Neutron Data Standards 2017. The evaluated cross
sections were also validated against the californium-252 spontaneous fission
neutron spectrum averaged cross sections, $\Sigma\Sigma$ (coupled thermal/fast
uranium and boron carbide spherical assembly) neutron spectrum averaged cross
sections, and small-sized LANL fast system criticalities. The changes in the
obtained evaluated cross sections from those in the JENDL-4.0 library are
within 4% ($^{241}$Pu), 3% ($^{233}$U, $^{240}$Pu), or 2% ($^{235}$U,
$^{239}$Pu). The newly evaluated $^{235}$U, $^{238}$U and $^{239}$Pu cross
sections agree with the IAEA Neutron Data Standards 2017 within 2% with some
exceptions.
