Application of the gross-count material basis set (GC-MBS) method to the analysis of CdZnTe spectra

Author

Rawool-Sullivan, Mohini W. ; Estep, Robert J. ; Johnson, M. William ; Murray, William

Author_Institution

Adv. Nucl. Technol. Group, Los Alamos, NM, USA

Volume

47

Issue

4

fYear

2000

fDate

8/1/2000 12:00:00 AM

Firstpage

1395

Lastpage

1398

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

Keywords

II-VI semiconductors; barium; caesium; gamma-ray spectra; neptunium; nuclear materials safeguards; semiconductor counters; uranium; ¹³³Ba; ¹³⁷Cs; ²³⁷Np; Ba; CdZnTe; CdZnTe spectra; Cs; Np; Pu; Pu burnup; U; depleted U; gross-count material basis set method; highly-enriched U; isotopic composition; net area method; polyethylene; response-function fitting; response-function method; source strength; Area measurement; Attenuation measurement; Building materials; Detectors; Lead; Organic materials; Performance analysis; Polyethylene; Shape measurement; Steel;

fLanguage

English

Journal_Title

Nuclear Science, IEEE Transactions on

Publisher

ieee

ISSN

0018-9499

Type

jour

DOI

10.1109/23.872984

Filename

872984