Both 235 U(n,f) and 238 U(n,f) cross sections are Neutron Standards in a broad energy region that includes neutron energies from 7.5 MeV up to 15 MeV. One of the most-often measured quantities is the ratio of the neutroninduced fission cross sections of 238 U to 235 U. Such ratio **data** in the region of interest, which will be denoted by R 8/5 , are weakly energy-dependent quantities. Their uncertainties, including possible components due to USU, are also expected to depend on energy. In this section the presence of USU for fission cross-section ratio **data** is investigated for neutron energies from 7.5 MeV up to 15 MeV. The **data** were taken from the Neutron Standards database, i.e., from the GMAP input database, covering the energy range of interest. The eleven **data** sets 5 that were considered are listed in Table XI of Appendix VI A, and are shown in Fig. 4. Note that for the exercise presented in this work all **data** sets were assumed to result from absolute ratio measurements.