FJFI_211 Introduction to Korean Advanced Nuclear Power Reactors
| Code: | FJFI_211 | ||||||
|---|---|---|---|---|---|---|---|
| Name: | Introduction to Korean Advanced Nuclear Power Reactors | ||||||
| Department: | Faculty of Nuclear Sciences and Physical Engineering | ||||||
| Duration in hours: | 26 lesson hours | ||||||
| Form of study: | Full-time | ||||||
| Instruction language: | TBA | ||||||
| Mode of delivery: | Lecture | ||||||
| Mode of completion: | None | ||||||
| Lecturer: |
|
||||||
| Supervisor: | Ing. Ondřej Novák, Ph.D. (ondrej.novak@fjfi.cvut.cz) | ||||||
| Minimum educational requirement: | Secondary (Úplné střední odborné vzdělání s maturitou (bez vyučení)) | ||||||
| Annotation: | Lecture will be given by prof Hyoung Kyu Cho This course provides a comprehensive introduction to the Korean pressurized water reactor (PWR), with emphasis on the Advanced Power Reactor (APR-type). It is designed for students who may be unfamiliar with Korean PWRs and progresses from the overall plant configuration to component-level detail. Topics include the reactor coolant system, steam and power conversion system, auxiliary systems, and engineered safety features. Operational procedures (startup, normal operation, shutdown) are presented alongside thermohydraulic phenomena during transients and accidents, the functions of safety systems, and representative safety analysis results. Prior exposure to introductory nuclear engineering, thermodynamics, and heat transfer is recommended but not required. |
||||||
| Structure: | preliminary lecture schedule 1 Overview, goals of course Reactor Coolant System (loop configuration, reactor pressure vessel) 2 Reactor Coolant System (Reactor core and nuclear fuel) Reactor Coolant System (Pressurizer and reactor coolant pump) 3 Reactor Coolant System (Steam generator) Steam & power conversion system 4 Steam & power conversion system Rankine cycle analysis 5 Auxiliary system (Circulating water system, Chemical and volume control system) Auxiliary system (Component cooling water system, Essential service water system) 6 Auxiliary system (Fuel storage and handling system) Engineered safety features (Containment, containment spray system) 7 Engineered safety features (Safety injection system) Engineered safety features (Shutdown cooling system, auxiliary feedwater system) 8 Plant protection system, Plant monitoring system. Plant control system 9 Reactor operation 10 Safety analysis of Korean PWRs 11 Safety analysis of Korean PWRs 12 Safety analysis of Korean PWRs 13 Thermal-hydraulic analysis of nuclear reactor components |
||||||
| Document: | Certificate | ||||||
| Date: | 19.02.2026 - 15.05.2026 | ||||||
| Venue: | Praha, V Holešovičkách 2, Praha 8 | ||||||
| Price: | Free | ||||||
| Note: | Lecture time will be every Thursday from 10:00 to 12:00 Texts APR1400 Standard Design Certification Application Design Control Document, Revision 3, Tier 1 and Tier 2, Korea Electric Power Corporation and Korea Hydro & Nuclear Power Co., Ltd (KEPCO/KHNP). https://www.nrc.gov/reactors/new-reactors/large-lwr/design-cert/apr1400/dcd |