Author Details

Mosunova, N.

Issue	Section	Title	File
Vol 63, No 2 (2016)	Nuclear Power Stations	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
Vol 64, No 7 (2017)	Nuclear Power Stations	System of closing relations of a two-fluid model for the HYDRA-IBRAE/LM/V1 code for calculation of sodium boiling in channels of power equipment
Vol 64, No 10 (2017)	Nuclear Power Stations	Experimental investigation of the impulse gas injection into liquid and the use of experimental data for verification of the HYDRA-IBRAE/LM thermohydraulic code
Vol 65, No 5 (2018)	Nuclear Power Plants	The EUCLID/V1 Integrated Code for Safety Assessment of Liquid Metal Cooled Fast Reactors. Part 1: Basic Models
Vol 65, No 8 (2018)	Heat and Mass Transfer, Properties of Working Fluids and Materials	Experimental Simulation of Hydrodynamics and Heat Transfer in Bubble and Slug Flow Regimes in a Heavy Liquid Metal
Vol 65, No 9 (2018)	Nuclear Power Plants	The EUCLID/V1 Integrated Code for Safety Assessment of Liquid Metal Cooled Fast Reactors. Part 2: Validation and Verification
Vol 66, No 5 (2019)	Nuclear Power Plants	The EUCLID/V2 Code Physical Models for Calculating Fuel Rod and Core Failures in a Liquid Metal Cooled Reactor
Vol 66, No 5 (2019)	Nuclear Power Plants	Verification of the EUCLID/V2 Code Based on Experiments Involving Destruction of a Liquid Metal Cooled Reactor’s Core Components