An experimental facility has been developed for short-half-life neutron activation studies. Sample material is transported between the irradiation position and the counting position by a constant-velocity cog belt. This facility has been used to measure the 53Cr(n,p)52V cross section relative to the 52Cr(n,p)52V cross section below 9.4 MeV, using elemental chromium metal as a sample material. The measured ratios and previously reported cross-section information for the 52Cr(n,p)52V have been used to derive values for the 53Cr(n,p)53V cross section. The 235U thermal-neutron fission spectrum average has been calculated from the differential results, and comparison is made with reported integral data.