FJFI_164 Introduction to APR reactors and their safety evaluations

Code: FJFI_164
Name: Introduction to APR reactors and their safety evaluations
Department: Faculty of Nuclear Sciences and Physical Engineering
Duration in hours: 8 lesson hours
Form of study: Full-time
Instruction language: TBA
Mode of delivery: Lecture
Mode of completion: Colloquium
Lecturer:
Jméno Kontakt
Ing. Ondřej Novák, Ph.D. ondrej.novak@fjfi.cvut.cz
Supervisor: Ing. Ondřej Novák, Ph.D. (ondrej.novak@fjfi.cvut.cz)
Minimum educational requirement: Secondary
Annotation:

Lectures are given by visiting professor Byongjo, Yun, Ph.D.ProfessorSchool of Mechanical EngineeringPusan National University Korea

Structure:

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 issues3.  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

Document: Certificate
Date: 22.04.2025 - 07.05.2025
Venue: Praha, V Holešovičkách 2, Praha 8, L-125
Timetable:
  • Tuesday: 14:00-16:30, L125 (*Praha, V Holešovičkách 2, Praha 8, L-125)
Price: Free
Note:

it is possible to visit only some lectures

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