Mathematical modeling of extraction of nitric acid, actinides, and fission products into 30% TBP in halogenated diluents using A.M. Rozen’s model


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Abstract

The effect of a series of halogenated diluents [bis(octafluoroamyloxy)methane, phenyl trifluoromethyl sulfone, methyl dodecafluoroheptyl ether, m-nitrobenzotrifluoride, hexachlorobutadiene, CHCl3, CCl4] on the extraction of spent nuclear fuel solution components [HNO3, U(VI), An(IV), Zr, and Tc] into 30% TBP was studied and mathematically described using improved A.M. Rozen’s model. Comparison with the TBP–paraffins extraction system was made.

About the authors

E. A. Puzikov

Khlopin Radium Institute

Author for correspondence.
Email: egor_puzikov@mail.ru
Russian Federation, 2-i Murinskii pr. 28, St. Petersburg, 194021

A. S. Kudinov

Khlopin Radium Institute

Email: egor_puzikov@mail.ru
Russian Federation, 2-i Murinskii pr. 28, St. Petersburg, 194021

I. V. Blazheva

Khlopin Radium Institute

Email: egor_puzikov@mail.ru
Russian Federation, 2-i Murinskii pr. 28, St. Petersburg, 194021

L. V. Sytnik

Khlopin Radium Institute

Email: egor_puzikov@mail.ru
Russian Federation, 2-i Murinskii pr. 28, St. Petersburg, 194021

D. N. Shishkin

Khlopin Radium Institute

Email: egor_puzikov@mail.ru
Russian Federation, 2-i Murinskii pr. 28, St. Petersburg, 194021

N. D. Goletskii

Khlopin Radium Institute

Email: egor_puzikov@mail.ru
Russian Federation, 2-i Murinskii pr. 28, St. Petersburg, 194021

B. Ya. Zilberman

Khlopin Radium Institute

Email: egor_puzikov@mail.ru
Russian Federation, 2-i Murinskii pr. 28, St. Petersburg, 194021


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