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THE SPECTRUM AND TEMPERATURE OF THE NEUTRON GAS IN A GRAPHITE-WATER REACTOR
E. Ya. Doil'nitsyn, A. G. Novikov
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Abstract
Spectrum characteristics of thermal neutrons stabilized in various moderators are evaluated. A mechanical neutron selector with a 256 channel time analyzer was used for measuring graphite -- water reactor thermal neutron spectra at temperatures from 300 to 800 deg K. The neutron spectra at a reactor power of 0.05% are plotted. Neutron gas temperatures measured using the spectral data and boron filters are plotted as function of reactor power (0.05,