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우승민,Sunil S. Chirayath,Massimiliano Fratoni 한국원자력학회 2018 Nuclear Engineering and Technology Vol.50 No.7
An analysis of a pyroprocessing safeguards methodology employing the Pu-to-244Cm ratio is presented. The analysis includes characterization of representative used nuclear fuel assemblies with respect tocomputed nuclide composition. The nuclide composition data computationally generated is appropriatelyreformatted to correspond with the material conditions after each step in the head-end stage ofpyroprocessing. Uncertainty in the Pu-to-244Cm ratio is evaluated using the Geary-Hinkley transformationmethod. This is because the Pu-to-244Cm ratio is a Cauchy distribution since it is the ratio oftwo normally distributed random variables. The calculated uncertainty of the Pu-to-244Cm ratio ispropagated through the mass flow stream in the pyroprocessing steps. Finally, the probability of Type-Ierror for the plutonium Material Unaccounted For (MUF) is evaluated by the hypothesis testing methodas a function of the sizes of powder particles and granules, which are dominant parameters to determinethe sample size. The results show the probability of Type-I error is occasionally greater than 5%. However,increasing granule sample sizes could surmount the weakness of material accounting because of thenon-uniformity of nuclide composition.