Evaluation of microscopic integral cross sections averaged in the uranium 235 thermal fission neutron spectrum (for 29 nuclear reactions relevant to neutron dosimetry and fast reactor technology)

For a number of (n.γ). (n,f), (n,n'), (n,p), (n,α) and (n,2n) nuclear reactions of
interest in technological applications, it has been attempted to assess the best experimental values and errors of the microscopic average cross-sections in the uranium-235 thermal fission neutron spectrum. This evaluation has been done in a way as independently as possible of any assumption regarding differential nuclear data, but the interrelations are indicated whenever necessary, The emphasis has been laid primarily on the relative internal consistency of the evaluated integral data rather than on the proposed absolute scale ; for the considered threshold reactions, this scale is presumably the most critically weiqhted by the accepted ²³⁵U (n,f) / ²³⁸U (n,f) integral cross-section ratio of 3.81 ±0.15.
The need for more decisive experimental clarification is suggested thoroughiy.