Informaçao sobre o Autor

Mosunova, N.

Edição Seção Título Arquivo
Volume 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
Volume 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
Volume 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
Volume 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
Volume 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
Volume 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
Volume 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
Volume 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

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