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Simulation of nuclear-fuel solvent-extraction reprocessing 7. Separation of macroscopic amounts of plutonium and uranium by displacement reextraction of plutonium in reprocessing fast-reactor fuel (section 1)

✍ Scribed by É. V. Renard; M. Ya. Zel'venskii


Publisher
Springer US
Year
1979
Tongue
English
Weight
525 KB
Volume
47
Category
Article
ISSN
1573-8205

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