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Monitoring of the Movement of a Melt of Fissioning Material in the Experimental Channel of a Pulsed Graphite Reactor IGR Using Small Neutron Detectors
Authors:N V Gorin  Ya Z Kandiev  A N Shcherbina  Zh R Zhotabaev  Yu M Kaz'min  V A Pakhnits  A P Vasil'ev  V M Malinkin  V A Pavshuk  Yu G Nikiporets
Affiliation:(1) Russian Federal Nuclear Center – All-Russia Scientific-Research Institute of Technical Physics, Russia;(2) Institute of Atomic Energy, National Nuclear Center of the Republic of Kazakhstan, Republic of Kazakhstan;(3) Scientific Research and Design Institute of Power Engineering, Republic of Kazakhstan;(4) Russian Science Center Kurchatov Institute, Russia
Abstract: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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