Nuclear Data for Calculation of Nuclear Reactors Antineutrino Spectrum

摘要

In summary, driven by the current scientific interest in nuclear reactor antineutnnos, as well as by the potential non-proliferation applications, the ENDF/B-VII.l decay data sub-library was updated to include relevant TAGS data and the thermal (235)~U fission yields were corrected. These data were used as input in the summation method allowing as to a) identify mam contributors to the antineutrino spectra, b) derive systematics of the IBD cross section integrated spectra, and c) more consistently predict the (235)~U electron and antineutrino spectra. It is expected that in the next few years, the calculation of antineutrino spectra following the fission of actinide nuclides will be sufficiently precise to make a firm assessment regarding the existence of sterile neutrinos Additionally, the neutrino detection technology will mature to the point of being applicable in non-proliferation situations.