Electron and antineutrino spectra from fragments of 235U, 239Pu, 241Pu fission by thermal neutrons and of 238U fission by fast neutrons

Stationary spectra of electrons and antineutrino of fission products of the main components of the reactor fuel 235U, 239Pu and 241Pu by thermal neutrons and 238U by neutrons of fission spectrum, are calculated. New nuclear and neutron data for fission fragments, as well as the latest recommendations on calculating their yields are used here, the effects of fragment burning out and delayed neutrons emission taken into account. The comparison with the results of other calculations and experiment is carried out, the reasons for desagreement are ananlyzed in detail; the errors of the obtained spectra are evaluated. The errors of electron and antineutrino U235U spectra of the present paper within low and intermediate energy range (1.5-6 MeV) lie within 10% limits, and further on they increase with the energy and can approach approximately 20%. The spectra of other fissile isotopes are the same as for 235U. But the calculation errors are much more essential. It is explained mainly by fewer experimental information on fission fragment yields of these isotopes. Cross section calculations averaged by the spectra of sup(235, 238)U, sup(239, 271)Pu antineutrino, carried out for the reaction of back neutron β-decay νsub(e)sup(-)+p→n+esup(+) have shown that the effect relations of each of the components to the effect from 235U for one fission act are equal to 1; 1.65; 0.705; 1.U7 respectively