<p>Accurate quantification in gamma-ray spectrometry requires precise correction for self-attenuation effects, especially in heterogeneous matrices. In this study, we determine the self-attenuation coefficient of a uranium ore sample (6.6 weight % uranium and approximate 93.4 weight % SiO<sub>2</sub>) using two methods: direct measurement from the ore’s intrinsic gamma ray emissions and an external Eu-152 source applied to the ore matrix. A correction multiplier is developed to reconcile deviations observed with increasing sample mass. The dual-method approach enhances reliability in determining radionuclide elemental concentration and/or raioactivities in high-Z materials.</p>

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Comparative evaluation of self-attenuation corrections in uranium ore: intrinsic versus Eu-152 gamma-ray techniques

  • E. Almaz,
  • C. Martin,
  • M. Sabry,
  • S. Landsberger

摘要

Accurate quantification in gamma-ray spectrometry requires precise correction for self-attenuation effects, especially in heterogeneous matrices. In this study, we determine the self-attenuation coefficient of a uranium ore sample (6.6 weight % uranium and approximate 93.4 weight % SiO2) using two methods: direct measurement from the ore’s intrinsic gamma ray emissions and an external Eu-152 source applied to the ore matrix. A correction multiplier is developed to reconcile deviations observed with increasing sample mass. The dual-method approach enhances reliability in determining radionuclide elemental concentration and/or raioactivities in high-Z materials.