Abstract
A prototype gamma-ray scanning system was designed to perform post-irradiation examination measurements of nuclear fuel. The system is composed of a coaxial high-purity germanium (HPGe) detector, a collimator, and mechanical positioning stages that translate the fuel sample across the front of the collimator. This paper documents the design process, modeling and the laboratory characterization performed to validate the system. The modeling of the system was done using the Monte Carlo N-Particle code with vendor-supplied design specifications, dimensional measurements, and X-ray radiographs of the HPGe detector. The characterization included measurements of calibrated radiation sources in different geometries, and calculations for absolute efficiency and dead time. Benchmark measurements were performed by scanning an irradiated fuel rodlet containing ten pellets of 4.9% enriched UO2 in zirconium alloy. These results were compared to simulated spectra to further help characterize the detector model. One goal of the system is to determine the number of fissions per gram of UO2 in the fuel; comparison of the results from this prototype system's assay of the irradiated fuel rodlet are in agreement with previously estimated results.
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Acknowledgements
This research was supported by the Advanced Fuels Campaign and the Office of Nuclear Energy of the U.S. Department of Energy. INL is operated for the U.S. Department of Energy by Battelle Energy Alliance under DOE contract DE-AC07-05-ID14517.
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Office of Advanced Fuels Technologies.
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Ocampo Giraldo, L.A., Holschuh, T.V., Thompson, S.J. et al. Design and validation of a gamma-ray scanning system for measuring irradiated nuclear fuel. J Radioanal Nucl Chem 331, 4919–4927 (2022). https://doi.org/10.1007/s10967-022-08479-8
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DOI: https://doi.org/10.1007/s10967-022-08479-8