The Use of Computer Codes for Assessing the Safety of Reactor Systems and Calculating the Thermohydraulic Parameters of Small Modular Reactors and VVER Reactors

Training Course “The Use of Computer Codes for Assessing the Safety of Reactor Systems and Calculating the Thermohydraulic Parameters of Small Modular Reactors and VVER reactors”, 30 h total Training modules 

1. Introduction to training course 

2. Nuclear power in Russia: history, current status, and trends 

3. Nuclear reactor technology – the base for the sustainable development of the country 

4. Main features of SMR concepts

5. Potential of SMR technology 

6. Main design features of light water SMRs 

7. Safety systems of water cooled SMRs 

8. KORSAR Code – overview and history of development. Basic features of KORSAR Code 

9. Results of verification, expert evaluation and certification of KORSAR Code 

10. Input files structure and principles of nodolization for KORSAR Code. Simulation of NPP circuit using graphical editor of models 

11. Demonstration of KORSAR Code simulation process. Hands-on tutorial 

12. Demonstration of simulation process using KORSAR Code 

13. Analysis of the obtained results. Evaluation of simulation errors 

14. Practical application experience of KORSAR/GP Code for VVER reactors safety assessment 

15. The role of CFD simulation in reactors safety system analysis 

16. Practical session on simulation using open source CFD software 

17. Practical session on simulation using open source CFD software 

18. Final test and discussion