Space-energetic distributions of fast neutrons in the materials of blanket and thermonuclear reactor shields

Spectra measurement of slowing-down neutrons with the initial energy 15 MeV in lead and graphite of thermonuclear reactor containment under certain geometrical conditions convnient for comparison with calculations are made. Neutron generation NG-200 is used as a neutron source. Flowsheet of experimenal fuel assemblies is presented. Precise technique of reduction of measured neutron spectra is mentioned. Measurement results of spatial and energy distributions of energy group neutrons 14.5-15.0, 14.0-14.5, 10.5-14.0, 6.5-10.5, 4-6.5, 3-4 MeV in graphite and lead are presented in a graphic form. Lengths of neutron relaxations are calculated. It is shown that neutron flow in all graphite thicknesses has the minimum in the energy range 11-13 MeV, and in all lead thickness - minimum in the range 9-14 MeV. The data obtained do not contadict the known data and specify them