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Volume 58, Nº 3 (2016)
РH process as a technology for reprocessing mixed uranium–plutonium fuel from BREST-OD-300 reactor
Shadrin A., Dvoeglazov K., Maslennikov A., Kashcheev V., Tret’yakova S., Shmidt O., Vidanov V., Ustinov O., Volk V., Veselov S., Ishunin V.
PDF
(Eng)
Volume 59, Nº 5 (2017)
A lumped parameter model of electrochemical reprocessing of spent nuclear fuel
Shults O., Simonenko V., Peshkichev I.
PDF
(Eng)
Volume 59, Nº 4 (2017)
Physicochemical principles of preparation of U(VI) carbonate solutions for extraction reprocessing in the Carbex process
Tsivadze A., Chekmarev A., Boyarintsev A., Stepanov S.
PDF
(Eng)
Volume 58, Nº 4 (2016)
Simulation of closed nuclear fuel cycle processes as a tool for the development and optimization of radiochemical technologies
Shmidt O., Makeeva I., Liventsov S.
PDF
(Eng)
Volume 61, Nº 6 (2019)
Preparation of Solid Solutions of Uranium and Cerium Oxides from Their Nitric Acid Solutions Using Microwave Radiation
Kulyako Y., Vinokurov S., Trofimov T., Pilyushenko K., Malikov D., Perevalov S., Savel’ev B., Dvoeglazov K., Shadrin A., Myasoedov B.
PDF
(Eng)
Volume 61, Nº 1 (2019)
Preparation of Powdered Uranium Oxides by Denitration of Nitric Acid Uranium Solutions Using UHF Radiation
Kulyako Y., Trofimov T., Pilyushenko K., Malikov D., Perevalov S., Vinokurov S., Savel’ev B., Myasoedov B.
PDF
(Eng)
Volume 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., Vazhenkov M., Stepanov S., Boyarintsev A., Tsivadze A.
PDF
(Eng)
Volume 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., Merkushkin A., Nekhaevskii S., Tyupina E.
PDF
(Eng)
Volume 61, Nº 5 (2019)
Thermodynamic Analysis of the Carbothermal Synthesis of (U, Pu)N
Peshkichev I., Bochkareva A., Kuropatenko V., Makeyeva I., Shults O.
PDF
(Eng)
Volume 60, Nº 4 (2018)
Synthesis of High-Density Pellets of Uranium Dioxide by Spark Plasma Sintering in Dies of Different Types
Papynov E., Shichalin O., Mironenko A., Ryakov A., Manakov I., Makhrov P., Buravlev I., Tananaev I., Avramenko V., Sergienko V.
PDF
(Eng)
Volume 59, Nº 3 (2017)
Removal of U(VI) from simulated liquid waste using synthetic organic resin
Massoud A., Waly S., Abou El-Nour F.
PDF
(Eng)
Volume 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., Kulyako Y., Blazheva I., Goletskii N., Zilberman B., Metalidi M., Petrov Y., Ryabkova N., Vinokurov S., Trofimov T., Myasoedov B.
PDF
(Eng)
Volume 59, Nº 6 (2017)
Determination of concentrations of fission products by ICP–AES in solutions from spent nuclear fuel reprocessing
Naumova Y., Sapozhnikova N., Egorova O., Lumpov A.
PDF
(Eng)
Volume 59, Nº 1 (2017)
Chemical-spectroscopic determination of impurity elements in concentrated salt products from pyrochemical reprocessing of spent nuclear fuel
Khamdeev M., Vasil’eva O., Kubasova L., Erin E.
PDF
(Eng)
Volume 58, Nº 3 (2016)
Commercial recovery of valuable radionuclides from spent nuclear fuel: Methods and approaches
Tananaev I., Myasoedov B.
PDF
(Eng)
Volume 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.
PDF
(Eng)
Volume 59, Nº 1 (2017)
Effect of carbon impurity in irradiated mixed uranium–plutonium nitride on the phase composition upon β−-decay of fission products
Bulatov G., Gedgovd K., Maslennikov A., Lyubimov D.
PDF
(Eng)
Volume 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., Goletskii N., Zilberman B., Fedorov Y., Kudinov A., Naumov A., Kukharev D., Ryabkov D., Shmidt O.
PDF
(Eng)
Volume 58, Nº 5 (2016)
A carbon composite based on pyrolyzed diphthalocyanines for immobilization of high-level waste from nuclear industry
Tikhonov V., Kapustin V., Lebedev V., Sovestnov A., Bairamukov V., Mishin K.
PDF
(Eng)
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