Measurement of the ⁵³Cr(n, p)⁵³V Cross Section Below 9.4 MeV Using a Sample Transport Facility

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.