Actions for EVALUATION OF THE ABSORPTION CROSS SECTION OF U-235 FISSION FRAGMENTS IN THE 0.025 - 10[sup 6] ev ENERGY RANGE AND CALCULATION OF FRAGMENT EFFECTS IN INTERMEDIATE REACTORS
EVALUATION OF THE ABSORPTION CROSS SECTION OF U-235 FISSION FRAGMENTS IN THE 0.025 - 10[sup 6] ev ENERGY RANGE AND CALCULATION OF FRAGMENT EFFECTS IN INTERMEDIATE REACTORS
The neutron absorption cross sections of those U/sup 235/ fission fragments whose radiative-capture thermal cross section does not exceed 10/sup 3/ barns are evaluated. Non-stable fragments of half life less than 100 days were not considered. Results were used to calculate the effect of fragments on intermediate reactor reactivity. The calculations were carried out for non- reflected reactors in the diffusion-age approximation. (W.D.M.)