Fast-reactor uranium-plutonium extraction by equilibrium water systems with 0.15?1 M HNO3 acidity

Vereshchagin, V. E.; Renard, É. V.

doi:10.1007/bf01120593

At Energy

1978

DOI: 10.1007/bf01120593

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Fast-reactor uranium-plutonium extraction by equilibrium water systems with 0.15?1 M HNO3 acidity

V. E. Vereshchagin¹,

É. V. Renard²

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Cited by 3 publications

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Physicochemical approach to the description of the distribution of macroquantities of Pu(IV) in extraction by tributylphosphate from nitrate solutions in the presence of complex formers applicable to the regeneration of spent nuclear fuel from fast reactors

Solovkin¹,

Rubisov²

1984

At Energy

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Fast-reactor uranium-plutonium extraction by equilibrium water systems with 0.15?1 M HNO3 acidity

Cited by 3 publications

References 2 publications

Physicochemical approach to the description of the distribution of macroquantities of Pu(IV) in extraction by tributylphosphate from nitrate solutions in the presence of complex formers applicable to the regeneration of spent nuclear fuel from fast reactors

Physicochemical approach to the description of the distribution of macroquantities of Pu(IV) in extraction by tributylphosphate from nitrate solutions in the presence of complex formers applicable to the regeneration of spent nuclear fuel from fast reactors

Calculation of steady-state regimes of technological extraction processes from data on the thermodynamics of Pu (IV) extraction with Tri-n-Butyl phosphate (TBP) from nitrate solutions

A New Approach to Simulation of Extraction Equilibria in the PUREX Process

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