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Title
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Vol 58, No 3 (2016)
Dissolution of WWER-1000 spent nuclear fuel in a weakly acidic solution of iron nitrate and recovery of actinides and rare earth elements with TBP solutions
Fedorov Y.S., Kulyako Y.M., Blazheva I.V., Goletskii N.D., Zilberman B.Y., Metalidi M.M., Petrov Y.Y., Ryabkova N.V., Vinokurov S.E., Trofimov T.I., Myasoedov B.F.
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(Eng)
Vol 59, No 5 (2017)
Simulation of the dynamic beyond-design-basis regime in an extraction–scrubbing unit consisting of mixer–settlers or centrifugal contactors in reprocessing spent nuclear fuel from nuclear power plants and of impurex process
Puzikov E.A., Goletskii N.D., Zilberman B.Y., Fedorov Y.S., Kudinov A.S., Naumov A.A., Kukharev D.N., Ryabkov D.V., Shmidt O.V.
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(Eng)
Vol 58, No 3 (2016)
Commercial recovery of valuable radionuclides from spent nuclear fuel: Methods and approaches
Tananaev I.G., Myasoedov B.F.
PDF
(Eng)
Vol 59, No 4 (2017)
Physicochemical principles of preparation of U(VI) carbonate solutions for extraction reprocessing in the Carbex process
Tsivadze A.Y., Chekmarev A.M., Boyarintsev A.V., Stepanov S.I.
PDF
(Eng)
Vol 59, No 4 (2017)
High-temperature interaction of components of spent uranium nuclear fuel with alkali metal carbonates in the course of voloxidation in the Carbex process
Chekmarev A.M., Vazhenkov M.V., Stepanov S.I., Boyarintsev A.V., Tsivadze A.Y.
PDF
(Eng)
Vol 59, No 1 (2017)
Chemical-spectroscopic determination of impurity elements in concentrated salt products from pyrochemical reprocessing of spent nuclear fuel
Khamdeev M.I., Vasil’eva O.N., Kubasova L.A., Erin E.A.
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(Eng)
Vol 59, No 6 (2017)
Determination of concentrations of fission products by ICP–AES in solutions from spent nuclear fuel reprocessing
Naumova Y.A., Sapozhnikova N.V., Egorova O.N., Lumpov A.A.
PDF
(Eng)
Vol 58, No 5 (2016)
A carbon composite based on pyrolyzed diphthalocyanines for immobilization of high-level waste from nuclear industry
Tikhonov V.I., Kapustin V.K., Lebedev V.T., Sovestnov A.E., Bairamukov V.Y., Mishin K.Y.
PDF
(Eng)
Vol 59, No 6 (2017)
How can the cost of spent fuel reprocessing be reduced and reliable isolation of all the wastes be ensured?
Pokhitonov Y.A.
PDF
(Eng)
Vol 58, No 3 (2016)
Calculation of the activity of uranyl nitrate and nitric acid in the H2O–HNO3–UO2(NO3)2–TBP–diluent system using Zdanovskii’s rule
Ochkin A.V., Merkushkin A.O., Nekhaevskii S.Y., Tyupina E.A.
PDF
(Eng)
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