摘要: A survey is given of the analysis actinide nuclides by means ofa-spectrometry in high-level radioactivity process solutions resulting from reprocessing spent U-Th fuel. Separation fission products and isolation nuclides228Th,231Pa,232U,237Np and238Pu are performed adsorption, ion-exchange, extraction chromatography techniques. After separation, samples for quantitative determination prepared electrodeposition measured using a silicon-surface barrier detector combined with multichannel analyzer. An error estimation given.
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