Analytic representation of the fission neutron spectra of²³⁵U and²⁵²Cf

Abstract

Analytic representations of the spectra in two forms—in the form of a model spectrum$(2\alpha ^{3/2} /\sqrt \pi )\sqrt E exp({\text{--}}\alpha E)$ and as a sum of nine model spectra$\alpha ^2 E exp(--\alpha E)$, where α_i=4.2.1.333.1.0.0.8.0.4.0.2.0.05. and 0.01-are obtained on the basis of representative sets of integral cross sections for the fission neutron spectra of²³⁵U due to thermal neutrons and spontaneous fission spectra of²⁵²Cf.2 tables. 5 references.