Simulation of natural circulation experiments for heavy liquid metal coolant using HYDRA-IBRAE/LM code
Author:
Funder
ROSATOM
Publisher
Elsevier BV
Reference32 articles.
1. 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;Alipchenkov;Therm. Eng.,2016
2. The EUCLID/V1 integrated code for safety assessment of liquid metal cooled fast reactors. Part 2: verification;Alipchenkov;Therm. Eng.,2018
3. Simulation of the processes occurring during steam generator tube rupture in the lead cooled reactor unit using HYDRA-IBRAE/LM code;Alipchenkov;Prog. Nucl. Energy,2022
4. Standard for Verificaton and Validation in Computational Fluid Dynamics and Heat Transfer,2009
5. Natural circulation studies in a lead bismuth eutectic loop;Borgohain;Prog. Nucl. Energy,2011
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