Optimization approach of gamma spectrometer measurements for accurate radioactive materials characterization
Author:
Affiliation:
1. Nuclear safeguardss and Physical Protection Department, Nuclear and Radiological Safety Research Center, Egyptian Atomic Energy Authority, Cairo, Egypt
Abstract
Publisher
National Library of Serbia
Reference26 articles.
1. Anilkumar, S., et al., Estimation of 235U Concentration in Some Depleted Uranium Samples by High Resolution Gamma-Ray Spectrometry Using 185 keV and 1001 keV Gamma-Energies of 235U and 234mPa, Journal of Radioanal Nucl. Chem, 274 (2007), 1, pp. 161-166
2. Fagan, D. K., et al., Statistical Methods Applied to Gamma-Ray Spectroscopy Algorithms in Nuclear Security Missions, Journal of Applied Radiation and Isotopes, 70 (2012), 10, pp. 2428-2439 [1]
3. Gunnink, R., et al., MGAU: A New Analysis Code for Measuring U-235 Enrichments in Arbitrary Samples, IAEA Symp. Int. safeguardss, Vienna, Austria, March 8-14 (1994), pp. 1-4
4. Gunnink, R., Arlt, R., Methods for Evaluating and Analyzing CdTe and CdZnTe Spectra, Nucl. Instruments Methods Phys Res A, 458 (2001), 1-2, pp. 196-205
5. Berndt, R., et al., 235U Enrichment or UF6 Mass Determination on UF6 Cylinders with Non-Destructive Analysis Methods, Nucl. Instruments Methods Phys Res A, 612 (2010), 2, pp. 309-319
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