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In the present work, the macroscopic characteristics of delayed neutrons have been calculated for the thermal and fast neutron induced fission of 235U, 238U and 239Pu by the summation method. The cumulative yields CY of 368 fission products from the latest version of JEFF, ENDF/B, JENDL, ROSFOND libraries, and Wahl data were used as the basic input data. The emission probabilities of delayed neutrons...
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