Abstract
The gross-count material basis set model (GC-MBS) for response-function fitting is applied to CdZnTe spectra. This method has been developed to solve for the isotopic composition of an unknown mixture of radionuclides attenuated through absorbers of unknown material. Results are presented for source strength and isotopic composition measurements of binary combinations of highly-enriched uranium (HEU), depleted uranium (DU), Np-237, Ba-133, Cs-137 and variable Pu burnups attenuated through a suite of absorbers ranging in Z-effective from polyethylene through Pb. Comparisons are made between the GC-MBS, net area method and simpler ordinary response-function methods.
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