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This evaluation demonstrates differing neutron flux results using correction factors in TRIGA reactors, indicating significant implications for measurement precision.
Neutron flux measurement for research reactor in-core is typically performed using the neutron activation method. In this study, an 197 Au sample The sample in this study used an 197 Au was irradiated to measure neutron.The neutron was calculated by determining the saturation activity of the irradiated sample, with correction factors applied for counting efficiency and uncertainty. This study analytically evaluated the influence of each correction factor on the neutron flux measurements in the TRIGA 2000 reactor core. The results indicate significant difference in flux calculations when using ϵ Overall Counting and ϵ Calibration. The averages value of neutron flux using ϵ Overall Counting is only 0.5% of the flux value using ϵ Calibration . The difference is due to the lack of consideration of intrinsic efficiency, which affects the full peak energy efficiency of the detector. As a result, ϵ Overall Counting is also affected by intrinsic efficiency.
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Roswita et al. (2025) studied this question.
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