| 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 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 |
|
