Computer simulation research of active neutron multiplicity counting and analysis

It is one of the important techniques of analytical uranium quality attributes to active neutron multiplicity counting and analysis. In this paper based on principle and measurement process, Monte Carlo particle transport code is used to establish computer model of neutron counter toward uranium. All-process simulation of active neutron multiplicity counting (ANMC) is achieved, which include processes of neutron generation, transportation, capture, MSR function. at last, getting the uranium quality attributes. The result shows the bias of data are smaller than 10%. (authors)