Abstract:
The method for measurement of
235U mass and burnup in fuel assembly in research reactors with comparison γ-Spectrum after irradiation is introduced in this paper. It also described the equipment, con-dition and experimental process of measurement IRT-3M fuel assembly in reactor IRT-MIFI in Russia, and presented relevant experiment result and its estimate of uncertainty. The result indicates the probability to ob-tain data of
235U mass in concentrated fuel assembly with uncertainty less than 2% by application of this method.
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