Characterizing self-attenuation in UO2 powder gamma spectrometry: development of a matrix-independent assay for mass and enrichment quantification in bulk nuclear material⋆

Accurate nondestructiv e assay (NDA) of bulk nuclear materials lacking a rigid physical form presents significant geometric challenges compared with standard item-form configurations such as sintered pellets, plates, or fuel rods. The quantification of unsealed uranium dioxide UO 2 powder is compromised by variable localized packing densities and severe internal self-attenuation of the primary 185.7 keV 235 U gamma-ray emission. This study investigates these limitations by characterizing UO 2 powder samples (0.4 to 4.0 wt% 235 U enrichment; 1–25 g uranium mass) using both a portable low-resolution NaI(Tl) and a high-resolution HPGe spectrometer. Empirical modeling of the specific count rate against areal density confirmed adherence to the integrated Beer-Lambert law, establishing a minimum physical thickness threshold of 1.0 cm to achieve infinite thickness saturation of 95%. Absolute 185.7 keV count rates below this geometric threshold are highly susceptible to density fluctuations, rendering them unreliable for direct mass or enrichment quantification in non-rigid matrices. To overcome this self-attenuation barrier, the highly penetrating 1001 keV emission from 234m Pa was validated as an internal bulk mass standard. Using the relative activity ratio (185.7 keV/1001 keV) successfully neutralized both structural matrix inconsistencies and discrepancies in intrinsic hardware efficiency. A comparative analysis between the two detection systems yielded a linear transfer function (R 2 > 0.97, slope = 0.68, intercept = 0.51). This methodology provides a detector-agnostic physical signature that significantly enhances bulk uranium verifications and lays the groundwork for accurately quantifying advanced non-item nuclear materials, such as molten salt fuels.

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Journal
Annals of Nuclear Energy
Published
2026-09-05
DOI
https://doi.org/10.1016/j.anucene.2026.112810
Primary Topic
Radioactive contamination and transfer
Type
article
Field-Weighted Citation Impact
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article

Characterizing self-attenuation in UO2 powder gamma spectrometry: development of a matrix-independent assay for mass and enrichment quantification in bulk nuclear material⋆

Etty Mutiara, Erlina Noerpitasari, Mohammad Subekti, Sihana Sihana et al.
Annals of Nuclear Energy
Radioactive contamination and transfer
article

Characterizing self-attenuation in UO2 powder gamma spectrometry: development of a matrix-independent assay for mass and enrichment quantification in bulk nuclear material⋆

Etty Mutiara, Erlina Noerpitasari, Mohammad Subekti, Sihana Sihana, Ahadi D. Prasetya, Didik Setiaji, Mohammad Alfarisie, Agus. Sunarto, Mohamad Sukron F. Husein, Fajar M. Ramadhan
article en

Abstract

Accurate nondestructiv e assay (NDA) of bulk nuclear materials lacking a rigid physical form presents significant geometric challenges compared with standard item-form configurations such as sintered pellets, plates, or fuel rods. The quantification of unsealed uranium dioxide UO 2 powder is compromised by variable localized packing densities and severe internal self-attenuation of the primary 185.7 keV 235 U gamma-ray emission. This study investigates these limitations by characterizing UO 2 powder samples (0.4 to 4.0 wt% 235 U enrichment; 1–25 g uranium mass) using both a portable low-resolution NaI(Tl) and a high-resolution HPGe spectrometer. Empirical modeling of the specific count rate against areal density confirmed adherence to the integrated Beer-Lambert law, establishing a minimum physical thickness threshold of 1.0 cm to achieve infinite thickness saturation of 95%. Absolute 185.7 keV count rates below this geometric threshold are highly susceptible to density fluctuations, rendering them unreliable for direct mass or enrichment quantification in non-rigid matrices. To overcome this self-attenuation barrier, the highly penetrating 1001 keV emission from 234m Pa was validated as an internal bulk mass standard. Using the relative activity ratio (185.7 keV/1001 keV) successfully neutralized both structural matrix inconsistencies and discrepancies in intrinsic hardware efficiency. A comparative analysis between the two detection systems yielded a linear transfer function (R 2 > 0.97, slope = 0.68, intercept = 0.51). This methodology provides a detector-agnostic physical signature that significantly enhances bulk uranium verifications and lays the groundwork for accurately quantifying advanced non-item nuclear materials, such as molten salt fuels.

Annals of Nuclear EnergyVol. 241
Universitas Gadjah Mada (ID), National Nuclear Energy Agency of Indonesia (ID)
Badan Riset dan Inovasi Nasional
Openalex Percentile: Top 13%
Radioactive contamination and transfer
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