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SPONTANEOUS FISSION CODE
The code outputs the magnitude and spectra of the resultant neutron sources. The delayed neutron spectra are taken from an evaluated library of 105 precursors. Spontaneous fission sources and spectra are calculated with evaluated half-life, spontaneous fission branching and Watt spectrum parameters for 44 actinides. The (α,n) spectra are calculated using an assumed isotropic angular distribution in the centre-of-mass system with a library of 107 nuclide decay alpha-particle spectra, 24 sets of measured and/or evaluated (α,n) cross sections and product nuclide level branching fractions, and functional alpha particle stopping cross sections for Z < 106. The code is also capable of calculating the neutron production rates due to (α,n) reactions induced by a monoenergetic beam of alpha particles incident on a slab of target material. SOURCES is a computer code that determines neutron production rates and spectra from (α,n) reactions, spontaneous fission and delayed neutron emission owing to the decay of radionuclides in homogeneous media, interface problems and three-region interface problems.