FJFI_164 Introduction to APR reactors and their safety evaluations
Code: | FJFI_164 | ||||
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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: |
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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 |
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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 |
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Document: | Certificate | ||||
Date: | 22.04.2025 - 07.05.2025 | ||||
Venue: | Praha, V Holešovičkách 2, Praha 8, L-125 | ||||
Timetable: |
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Price: | Free | ||||
Note: | it is possible to visit only some lectures |