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<dc:title xml:lang="fr">Spectrométrie gamma au laboratoire et in situ : développements et applications environnementales</dc:title>
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<dc:subject xml:lang="fr">Auto-absorption</dc:subject>
<dc:subject xml:lang="fr">Radioprotection</dc:subject>
<dc:subject xml:lang="fr">Radium équivalent</dc:subject>
<dc:subject xml:lang="fr">Dose absorbée</dc:subject>
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<dc:subject xml:lang="en">Self-absorption</dc:subject>
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<dcterms:abstract xml:lang="fr">La spectrométrie γ dose en une seule mesure tous les émetteurs γ dans un échantillon. L’auto-absorption des rayonnements γ dans des échantillons se manifeste par des pertes ou des gains d'impulsions. Pour caractériser une nouvelle géométrie de comptage, des améliorations du dispositif existant ont été apportées par des simulations MCNPX. Avec ce nouveau dispositif nous avons pu spécifier les doses absorbées et efficaces annuelles ainsi que les facteurs de conversion de dose des radioisotopes naturels pour des matériaux de construction et des prélèvements de sols. Des simulations ont montré l’influence des seuils de détection des rayonnements γ donc sur les facteurs de conversion de dose et la nécessité d’une mise à jour de ces facteurs. L’analyse par spectrométrie γ in situ du sol fait appel à des efficacités de détection simulées par MCNPX pour une source aux dimensions semi-infinies. Une application a été réalisée autour d’une centrale nucléaire et une autre pour une société.</dcterms:abstract>
<dcterms:abstract xml:lang="en">Γ-ray spectrometry enables determining all γ-ray emitters in a sample with a single measurement. Self-absorption of γ-rays in samples is manifest by a loss or a gain of pulses that results in a poor estimation of the counting efficiency. To characterize a new counting geometry improvements of the existing set-up were made with MCNPX simulations. With the new geometry we could specify absorbed and annual effective doses as well as dose conversion factors for the natural radioisotopes of several building materials and soil samples. Simulations show the influence of detection limits of γ-radiation on dose conversion factors and the need for updating these factors. γ-ray measurements of soil in situ require different counting efficiencies simulated by MCNPX for a semi-infinite source. Two in-situ soil analyses were made, one around a nuclear power and the other for a private company.</dcterms:abstract>
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