E. V. Usov

Fundamentals, current state of the development of, and prospects for further improvement of the new-generation thermal-hydraulic computational HYDRA-IBRAE/LM code for simulation of fast reactor systems

V. M. Alipchenkov, A. M. Anfimov, D. A. Afremov et al. · Thermal Engineering · 2016 · 29 citations

Engineering, Nuclear Engineering, Physics +17

Fuel Pin Melting in a Fast Reactor and Melt Solidification: Simulation Using the SAFR/V1 Module of the EVKLID/V2 Integral Code

E. V. Usov, V. I. Chukhno, I. A. Klimonov et al. · Atomic Energy · 2018 · 25 citations

Engineering, Computational Engineering, Nuclear Engineering +17

SAFR/V1 (EVKLID/V2 Integral Code Module) Aided Simulation of Melt Movement Along the Surface of a Fuel Element in a Fast Reactor During a Serious Accident

E. V. Usov, V. I. Chukhno, I. A. Klimonov et al. · Atomic Energy · 2018 · 25 citations

Engineering, Computational Engineering, Nuclear Engineering +17

The EUCLID/V2 Code Physical Models for Calculating Fuel Rod and Core Failures in a Liquid Metal Cooled Reactor

V. S. Zhdanov, I. A. Klimonov, I. G. Kudashov et al. · Thermal Engineering · 2019 · 22 citations

Engineering, Computational Engineering, Nuclear Engineering +17

Lead coolant modeling in system thermal-hydraulic code HYDRA-IBRAE/LM and some validation results

N. A. Mosunova, V. M. Alipchenkov, V. F. Strizhov et al. · Nuclear Engineering and Design · 2019 · 20 citations

Engineering, Computational Engineering, Computational Heat Transfer +14