Professor’s Profile
Oh Ji-Yong
- Major : Nuclear System Design and Safety
- Professor Associate Professor
- Office : Room 416, Main Bldg
- Phone : +82-52-712-7118
- Email : jiyong.oh@kings.ac.kr
Educational Background
• Ph.D., Nuclear Science and Engineering, MIT (2008.2)
• BS., Nuclear Engineering, Seoul National University (1998.2)
Professional Experience
• Associate Professor, KINGS NPP Department (2026-Present)
• Project Manager of APR1000 Standard Design, KHNP (2023-2025)
• Licensing Leader, APR1400 NRC Design Certification, Washington, KHNP (2015-2020)
• Senior Manager/Staff, System reliability engineering Team, KHNP (2008-2013)
• Staff, NPP operation and engineering, KHNP (2001-2008)
Research
ARENA (Advanced Reliability Engineering for Nuclear Applications) Lab
The ARENA Laboratory specializes in the development of innovative commercial nuclear systems and the optimization of operational safety. We conduct advanced research to improve Emergency Operating Procedures (EOP) and Severe Accident Mitigation Guidelines (SAMG) strategies utilizing high-fidelity simulators. Furthermore, our expertise extends to the development and practical implementation of diverse reliability engineering programs tailored for a wide range of nuclear applications.
1. Nuclear system design and safety analysis
- Innovative Commercial Nuclear System Design
(PROMETEUS, APR1000, SMART100, i-SMR, etc.)
2. Nuclear power operation optimization
- Operation strategy optimization using simulator
- Emergency Operating Procedure (EOP) and Severe Accident Mitigation Guideline (SAMG) optimization
3. Reliability engineering for nuclear applications
- PRA model development and Risk-Informed Application (RIA)
- Risk-Informed & Performance Based Regulation (RIPBR)
- Risk and cost analysis using Level 3 PRA, SAMDA and ALARP
- Equipment Reliability (ER), Maintenance Rule (MR), SPV (Single Point Vulnerability), RAP (Reliability Assurance Program), etc.
Lab Members
Radioactive Waste and Spent Fuel Management
Introduction To the Courses
Course Code: Nuclear Reactor Design and Safety
Introduction
This course provides a comprehensive overview of nuclear power plant design and safety. First, students will study the general principles of reactor design, followed by an introduction to the US NRC Design Certification (DC), the European Utility Requirement (EUR) review, and the Korea Regulatory Standard Design Approval (SDA) process. The course then focuses on regulatory requirements and key issues related to reactor safety as outlined in Chapters 15 and 19 of the APR1400 Safety Analysis Report (SAR). Finally, the curriculum covers practical aspects of reactor operation, including human factor engineering (HFE).
Course Objectives
① Understand the fundamental knowledge of nuclear reactor design and safety
② Understand the overall processes of NRC-DC, EUR, and SDA
③ Understand the regulatory requirements and key issues related to reactor safety, with a focus on safety analysis.
Student Outcomes
Term project report, Classroom presentation
Publications, Projects and Awards
Journal Papers
· J. Oh, APR1000, The Best Energy Solution for The Next Century in the Czech Republic, Czech Nuclear Energy Journal (2023)
· H. Moon, J. Oh, Risk reduction design alternatives for low-power and shutdown operation of a 1500 MWe Advanced Power Reactor with a Passive Auxiliary Feedwater System, Progress in Nuclear Energy (2020)
· J. Oh, S. Hwang, Risk-Informed Approach for Design Optimization during Low Power and Shutdown Operation, Annals of Nuclear Energy (2019)
· S. Hwang, J. Oh, Development of Optimized L1 & L2 PSA Model for APR1400 NPPs Using U.S. SOARCA Project Methodology, Annals of Nuclear Energy (2018)
Conference Papers
· J. Oh, W. Seol, The Safety Classification and Engineering Design Rule of the APR1000, ANS (2025)
· J. Oh, W. Seol, B. Kim, The Performance and Safety analysis of Passive Safety Features in the APR1000, ASRAM (2025)
· W. Seol, J. Oh, Analysis of Operational Effects of External Water Injection During Extended Loss of AC Power under Hazard conditions, ASRAM (2025)
· J. Oh, W. Seol, APR1000 Design and Its Design Optimization using PSA, ASRAM (2023)
· D, Hwang, J. Oh, Assessment of APR1000 Standard Design by European Utility Requirement Rev. E, ICAPP 2023
· J. Oh, H. Moon, H. Kim, Risk-Informed Design Change of an Advanced Reactor in LPSD Operation, Probabilistic Safety Assessment and Management Conference (2014)
Awards
Minister’s Award from the Ministry of Trade, Industry and Energy (2019) : Outstanding Contribution to the Acquisition of the APR1400 NRC Design Certification (DC)
President & CEO Award, Korea Hydro & Nuclear Power (KHNP) (2023) : Outstanding Contribution to the Acquisition of the APR1000 EUR Certification
Patents
· Cleaning apparatus for nuclear fuel assemblies (patent registration No. 10-2649024) (2024)
· Long-term cooling recovery equipment to prevent fluid backflow after a loss of coolant accident in a nuclear power plant and operation method thereof (10-2733192) (2024)
· Long-term cooling recovery equipment after nuclear power plant cooling water accident and operation method thereof (10-2733184) (2024)
· Method for responding over-pressure accident of coolant system in nuclear power plant and system therefor (10-2649452) / PCT, EP, US patent applied (2024)
· Method for responding loss of coolant accident in nuclear power plant and system therefor (10-2649451) / PCT, EP, US patent applied (2024)
· System for long term cooling of nuclear power plant and Method for long term cooling using the same (10-2718588) (2024)
· System for cooling and ventilation of containment building using coolant in PAFS tank and Method for cooling and ventilation using the same (10-2632043) (2024)
· System for coolant feeding and ventilation using coolant in PAFS tank and Method for coolant feeding and ventilation using the same (10-2649450) (2024)
· System for coolant feeding to steam generator using coolant in PAFS tank and Method for coolant feeding using the same (10-2647479) (2024)
· Direct cooling water filling system of nuclear reactor containment building (10-2557539) (2023)
Projects
· APR1000 Standard Design Approval Report (2024-2025), KHNP
· APR1000 Standard Design Development and EUR Certification Report (2021-2024), KHNP
· SMART100 Development and SDA Report (2015-2021), KHNP
· Evaluations and Design Enhancements to Incorporated Lessons Learned from Fukushima Dai-Ichi Nuclear Accident (2015-2021), KHNP
· Shutdown Evaluation Report for APR1400 (2015-2021), KHNP
· Probabilistic Risk Assessment Summary Report for APR1400 (2015-2021), KHNP
· Severe Accident Mitigation Design Alternatives for APR1400 (2015-2021), KHNP
· Reliability Assurance Program for APR1400 (2015-2021), KHNP