Multilevel parametrization of the 239Pu total and fission cross sections in the resonance neutron energy range

Results are presented of multilevel analysis of data on neutron transmission through 239Pu samples of different thickness in the energy range from 4 to 50 eV the analysis being conducted based on the Adlerov scheme in the S-matrix theory. Parameters of the total cross section and fission cross section of 16 resonances in the considered energy range as well as the mean group total cross section and fission cross section and factors of their resonance self-shielding versus the cross section dilution at 300 K are given. It is concluded that the obtained experimental data on transmission may be used in producing evaluated files of 239Pu nuclear data, while the mean group cross sections obtained on their base as well as the factors of resonance self-schielding may be obtained when developing new systems of group constants