In order to meet the international community's requirements of nuclear safeguards for the special fissionable material plutonium in spent fuel assemblies,and to provide nuclear material information continuously,it is particularly important to study non-destructive analysis techniques for measuring the plutonium content in spent fuel assemblies.This article adopts the active non-destructive assay,using pressurized water reactor spent fuel assemblies as the measurement object and D-D neutrons as active interrogation source,to carry out the design and research of a plutonium content measurement device for spent fuel assemblies.Using the MCNPX software,simulations were conducted on key parameters such as the distance between the neutron generator and the detector assembly,the moderator material and its thickness of the neutron generator,the height difference between the detector assembly and the neutron generator,and the moderator thickness of the detector assembly in the measurement device,with the aim of maximizing the detector counting rate and making the counting rates of each detector as consistent as possible.This study lays the foundation for the research and experiments of neutron interrogation technology for measuring plutonium content in spent fuel assemblies.
维普
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