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