Technological Aspects of AES-2006 (VVER-1200). Development of Nuclear Curricula on VVER Technology

The course is aimed at professors, lecturers, and researchers involved in the initiation or development of nuclear curricula in universities of countries embarking on nuclear power programmes, in particular, seeking to develop nuclear power with Russian design VVER-1200 reactors. MAIN TOPICS Topic

 1. Design of NPP with VVER. Russian Experience Topic 

2. Engineering Aspects of Nuclear Fuel Topic 

3. Management of VVER-1200 fuel Topic 

4. VVER-1200 Reactor and its Elements Topic 

5. VVER-1200 Reactor Monitoring and Control Topic 

6. AES-2006 Reactor Island Design Topic 

7. AES-2006 Safety Systems Topic 

8. AES-2006 Design Conditions Topic

 9. Computer Codes for Safety Analysis of VVER Reactors Topic 

10. Development of Nuclear Curricula on VVER Technology Facility Visit to AES-2006 NPP (for Russia-based courses)