Content
You can choose from three individual seminars:
1. Introduction to the APR (Advanced Power Reactor) – 22.4.
• Introduction of Korean Nuclear Reactor Development
• Major features of the reactor systems, component design, engineered safety features, etc.
2. New Safety Systems Adopted in the APR1400 and Experimental Program for Their Development – 29.4.
• Introduction of new safety features and experimental programs to resolve design and license issues
3. Passive Safety Systems adopted in the APR and Experimental Program for Their Development – 6.5.
• Design overview of PAFS (Passive Auxiliary Feedwater System) for APR+ and PCCS (Passive Containment Cooling System) for IPOWER, and experimental programs for their development
• Heat transfer model development and its application to 1D safety analysis codes
Venue: FNSPE CTU, Department of Nuclear Reactors, V Holešovičkách 2, Prague 8, room L-125 (MAP)
Lectures are free but it is possible to visit only some lectures by one person.
Contact person: This email address is being protected from spambots. You need JavaScript enabled to view it.
Additional information