O. V. Shmidt

РH process as a technology for reprocessing mixed uranium–plutonium fuel from BREST-OD-300 reactor

A. Yu. Shadrin, A. G. Maslennikov, V. A. Kashcheev et al. · Radiochemistry · 2016 · 50 citations

Engineering, Chemical Engineering, Nuclear Engineering +16

Modern Trends in Spent Nuclear Fuel Reprocessing and Waste Fractionation

Svetlana V. Gutorova, M. V. Logunov, Yu. A. Voroshilov et al. · Russian Journal of General Chemistry · 2024 · 35 citations

Engineering, Chemistry, Nuclear Engineering +16

Next Generation Design Codes for a New Technological Platform for Nuclear Power

L. A. Bolshov, N. A. Mosunova, V. F. Strizhov et al. · Atomic Energy · 2016 · 14 citations

Engineering, Design, Nuclear Engineering +16

Mathematical Simulation of Steady-State Concentration Profiles in Extraction Cascades for Reprocessing NPP Spent Fuel Using TBP-Compatible Processes (SUPERPUREX)

E. A. Puzikov, B. Ya. Zilberman, Yu. S. Fedorov et al. · Radiochemistry · 2004 · 12 citations

Engineering, Chemical Engineering, Environmental Engineering +11

Influence of temperature on the extraction of actinides from nitric acid solutions into 30% TBP: Description within the framework of a new model

E. A. Puzikov, B. Ya. Zilberman, Yu. S. Fedorov et al. · Radiochemistry · 2015 · 11 citations

Natural Sciences, Chemistry, Analytical Chemistry +10