I. G. Kudashov

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

A Step in the Verification of the Hydra-Ibrae/LM/V1 Thermohydraulic Code for Calculating Sodium Coolant Flow in Fuel-Rod Assemblies

E. V. Usov, I. G. Kudashov, N. A. Mosunova et al. · Atomic Energy · 2015 · 14 citations

Engineering, Mechanical Engineering, Physics +13

Experiment-Based Verification of the SAFR/V1 Module of the EVKLID/V2 Integral Code for Thermal Breakdown of Fuel Pins in a Fast Reactor

E. V. Usov, V. I. Chukhno, I. A. Klimonov et al. · Atomic Energy · 2018 · 13 citations

Engineering, Nuclear Engineering, Heat Transfer +14