Monitoring of the Movement of a Melt of Fissioning Material in the Experimental Channel of a Pulsed Graphite Reactor IGR Using Small Neutron Detectors
2002
It is shown that fuel elements consisting of a fissioning material can be simulated from the standpoint of the influence on the characteristics of the neutron field in the experimental channel of a pulsed graphite reactor by models fabricated from paraffin mixed with boric acid. It is suggested that a method be developed for monitoring the movement of the melt in the experimental channel of a pulsed graphite reactor on the basis of signals from small neutron detectors. It is suggested that the model components be melted in a pulsed graphite reactor by radiation heating by neutrons. In the future the method should be refined in experiments with actual assemblies.
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