Verification of the Evaluated Fission Product Yields Data from the Neutron Induced Fission of ²³⁵U, ²³⁸U and ²³⁹Pu Based on the Delayed Neutron Characteristics

For this case, the microscopic characteristics have been used, such as the cumulative yields of fission products, the probabilities of delayed neutron emission and the half-lives of their precursors. As a result for each database of the cumulative yields of fission products four values of the absolute total delayed neutrons yields νd and four values of the average half-life of delayed neutron precursors 1/2> were obtained. For each combination of data sets ''CY - (P_n,T_1/2)'' a model curve of delayed neutron activity was calculated for the ²³⁵U(n_th,f) reaction. The analysis of the results based on the comparison of the obtained delayed neutron macroscopic parameters v_d and 1/2> with the appropriate evaluated data allowed to study the sensitivity of the macroscopic delayed neutron parameters (v_d, T_1/2) to the microscopic delayed neutron data sets (P_n,T_1/2) for each of the considered fission reactions. (author)