Measurement of the ²³⁵U Neutron-Induced Fission Cross Section at 14.1 MeV

The ²³⁵U neutron-induced fission cross section was measured at a neutron energy of 14.1 MeV using the time-correlated associated-particle technique with the ³H(d,α) n reaction at the National Bureau of Standards 3-MV Van de Graaff Laboratory. The areal density and total mass of the ²³⁵U deposits were measured relative to the standard ²³⁵U reference deposit (Los Alamos National Laboratory Spare Number 1) using thermal-neutron-induced fission counting. The total mass was also determined from the alpha-particle decay rate. The measured ²³⁵U cross section at 14.1 ± 0.1 MeV is 2.080 ± 0.030 b where the uncertainty is one standard deviation. This value agrees within 1% with other recent measurements using this technique and with the ENDF/B-V evaluation.