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Experimental validation of a nuclear forensics methodology for source reactor-type discrimination of chemically separated plutonium

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The methodology uses measured values of intraelement isotope ratios of plutonium and fission product contaminants. MCNP radiation transport codes were used for various reactor core modeling and fuel burnup simulations. A reactor-dependent library of intra-element isotope ratio values as a function of burnup and time since irradiation was created from the simulation results. | Experimental validation of a nuclear forensics methodology for source reactor-type discrimination of chemically separated plutonium

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