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- W2064718984 abstract "Abstract An analytical scheme is described which allows of the sequential separation of the elements remaining after large neutron doses have been absorbed in 1 mg of a fissile element. The products isolated were in a form amenable to the determination of isotopic abundances by solid source mass-spectrometric methods; solvent extraction, ion-exchange, partition chromatographic and simple precipitation methods were used to achieve this end." @default.
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- W2064718984 title "A sequential analytical scheme for the carrier-free separation of microgram quantities of individual fission product and actinide elements from highly burnt-up fuels" @default.
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