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Professor’s Profile

Lim Hak Kyu

  • Major : NPP Risk Management, PRA and Reliability Engineering, NPP Safety
  • Professor Dean of Academic Affairs / Professor
  • Office : Room 320, Main Bldg
  • Phone : +82-52-712-7311(lab)7169(dean)
  • Email : hklim@kings.ac.kr

Educational Background

•  Ph.D., Mechanical Engineering, UCLA (1994.5)
•  MS, Mechanical Engineering, Seoul National University (1987.2)
•  BS. Mechanical Engineering, Seoul National University (1985.2)

Professional Experience

•  Associate professor, KINGS (2016.6~present)
•  Senior Researcher and Manager of PRA team, KEPCO-E&C (1994.11-2016.5)
•  Researcher, HVAC lab. KAIST (1988.3~1989.6)

Home Research

Research

[Risk-informed Performance-based Regulations and Approach]

[Risk-informed Performance-based Regulartion and Approach (RIPBR&A) has been widely applied in nuclear power plant (NPP) design and operation, based on NPP operation experiences since 1960's. To achieve safer and more efficient NPP, RIPBR&A has been a backbone of NPP design and opearation.]

 

[Related Publication]
1. Fery Putrawan Cusmanri and Hak-kyu Lim, "A Study on the Licensing Process for the Floating Nuclear Power Plant in Indonesia: A Suggestion for the Revision of Government Regulation Regarding Nuclear Power Plant Licensing," Energies, MDPI, 2024
2. Oluwadamilare Timothy Fasogbon and Hak-kyu Lim, “Assessing PRA Quality for Risk-Informed Activities: Insights from Regulatory Guides and Standards and Their Potential Application in Nigeria\'s Nuclear Regulations,” KNS Autumn Conference, 2024
3. Fery Putrawan Cusmanri and Hak-kyu Lim, “Initiating Event Analysis for Floating Nuclear Power Plant: Tsunami Case,” KNS Autumn Conference, 2024
Selection of Indonesia Potential Sites for Nuclear Program Using Reactor Technology Assessment," 
4. Fery Putrawan Cusmanri and Hak-kyu Lim, "Selection of Indonesia Potential Sites for Nuclear Program Using Reactor Technology Assessment," 에너지공학, 한국에너지공학회, 2024.

[Probabiolistic Risk Assessment]

[Probabilistic Risk Assessment (PRA), a.k.a. Probabilistic Safeety Assessment (PSA, is a unique technique for quantification of risk for NPPs. PRA was introduced as a research topic in 1970's and recently, it becomes one of key technology to ensure NPP safety.  PRA has been evolved based on NPP operational experiences and its practical applications. Thus, to perform PRA and understand PRA result correctly, various aspects of PRA should be considered carefully.]

 

[Related Publication]
1. 박종훈, 임학규, “Effects of house load operation on PSA based on operational experiences in Korea,” Nuclear Engineering and Technology, KNS, 2020
2. 임학규, “A Simple Approach to Calculate CDF with Non-rare Events in Seismic PSA Model of Korean Nuclear Power Plants,” Journal of the Korean Society of Safety, KOSOS, 2021
3. Mutallab Musa Ahmed, Diogo T. F Pires, Obuya Ogwenu Alwala, and Lim Hak Kyu, "Comparative Study of Performance Influencing Factor in IDHEAS-G and SPAR-H," KNS Autumn Conference, 2023

[PRA Applications]

[Since the introduction of PRA, PRA hase been widely used for safety enhacement with efficient NPP design and operation. Each application has its spectific approach with a very strong common concept how to manage NPP risk.]

 

[Related Publication]
1. 조주상, 임학규, “A Study on Intensive QA Inspection using Information from Risk-Informed Classification of SSCs,” KNS Srping Conference, 2022
2. 정민신, 정동환, 임학규, “A Review on the Scope of Accident Management in the  Accident Management Plan of Nuclear Power Plant,” KNS Spring Conference, 2021
3. 박지효, 임학규, "Coping Duration Assessment Using RG1.155 Methodology on Shin-kori 5&6," KNS Autumn Conference, 2020

Home Lab Members

Lab Members

Graduate Students

Class of 2025

  • Fasogbon Oluwadamilare Timothy,    Implementing Risk-Informed Decision-Making: A Proposed Roadmap for Nuclear Newcomer Countries
  • 곽종훈(Kwak Jong-hoon),    Identification of Maintenance Issues and Strategic Improvement Measure for Nuclear Power Plants in Korea
  • 이현중(Lee Hyun-joong),    Enhancing Refueling Outage Efficiency in South Korea: A Comparative Study with U.S. Practice
  • 권오면(Kwon Oh-myeon),    A Study on the Need for Risk-Informed and Performance-Based Regulation in Korea Compared with Nuclear Regulation in U.S
  • 김현성(Kim Hyeon-seong),    A Study on Turbine Missile Risks in Nuclear Power Plants based on Probabilistic Risk Assessment Approach
  • Ondiegi Kapis Goga,    Assessing Grid Reliability for Optimal Integration of System-Integrated Modular Advanced Reactor Technology (SMART) for Kenya: A Case of the Nairobi Distribution Network
  • Fery Putrawan Cusmanri,    Selection of Initiating Events for Floating Nuclear Power Plant: The Case Study of Tsunami in Indonesia

 

 

Alumni

Class of 2024

  • Diogo Tertuliano Fernandes Pires,    Estimation of Human Error Probability during SGTR Accident in Angra-2 NPP using SPAR-H and IDHEAS-ECA
  • Obuya Ogweno Alwala,    Qualitative Study of Performance Influencing Factors for Explicit Description of Organizational Factors in Human Reliability Analysis
  • Mutallab Musa Ahmed,    Dependency Analysis of Human Failure Events in Steam Generator Tube Rupture: A Comparative Study using SPAR-H and IDHEAS-DEP

 

 

Class of 2023

  • 박신영(Park Sinyoung),    A Study on Nuclear Power Plants Regulation Based on Risk Informed Approach
  • 고상현(Ko Sang-Hyun),    Scenario Development for SFP PRA During Transitional Period of Decommissioning
  • 홍영진(Hong Young Jin),    System Analysis for SFP PRA During the Transitional Period of Decommissioning
  • 최순형(Choi Soon-hyeong),    Re-estimate of Human Failure Events in APR1400 PRA from Operator Viewpoint
  • 조주상(Cho Ju-sang),    A Study on Intensive QA Inspection Using Information from Risk-Informed Classification of SSCs

 

 

Class of 2022

  • 김정민(Kim Jung-min),    Consistent Human Reliability Analysis of Mobile Equipment Using Various Methods
  • 정민신(Jung Min-shin),    A Study on the Identification of Additional Initiating Events to be Considered in the Design Process
  • 정동환(Jung Dong-hwan),    Study on the Application of the Common Cause Failure (CCF) Between EDG and AAC DG

 

 

Class of 2021

  • 박지효(Park Gee-hyu),    Coping Duration Assessment Using RG 1.155 Methodology on Shin-kori 5&6
  • 이향성(Lee Hyang-seong),    A Study on Fire Safe Shutdown Circuit Analysis
  • 정동현(Jeong Dong-hyun),    Review of Alternative Treatment for Application of Risk-Informed Categorization

 

 

Class of 2020

  • 박종훈(Park Jong-hoon),    The Effects of the House Load Operation on NPP from PRA Perspective
  • 박주일(Park Joo-il),    Human Error Probabilities Estimate for MACST Equipment in Response to APR 1400 Extended Loss of AC Power
  • 류효선(Ryu Hyo-sun),    Human Error Probability Quantification on Seismic Events; MACST Equipment for APR1400
  • Jonathan Amfoh Blankson,    Qualitative Human Reliability Assessment of FLEX Strategies (Phase 3) in an ELAP Utilizing SHERPA for Risk-Informed Decision Making

 

 

Class of 2019

  • Sigit Nugroho Pamunakas,    Applying the Cognitive Reliability and Error Analysis (CREAM) for FLEX Strategies in Response to APR1400 Extended SBO
  • Sainbuyan Sengee,    Human Reliability Analysis for FLEX Strategies in Response to Extended SBO Using THERP/CBDTM and Comparison of PSF with ATHEANA
  • Mohammed Bello Baba,    Human Reliability Analysis for FLEX Strategies in Response to Extended SBO Using THERP/CBDT and IDHEAS Methods
  • MD Tanvir Hasan,    Human Error Quantification for FLEX Strategies Using SPAR-H and Comparison of Methods of Dependency Consideration in Human Reliability Analysis

 

 

Class of 2018

  • Shaaban Abdalla Selo Mohamed,    Developing Flex Strategy for Radiological Emergency Preparedness and Response Plan Using PRA Model
  • Md. Golam Shahinoor Islam,    Comparative Study of FLEX Strategies for Extended Station Blackout (SBO) Using PRA
  • 손현준(Son Hyun-joon),    FLEX Effectiveness Study Under the Long-Term SBO by PRA

Radioactive Waste and Spent Fuel Management

Home Courses

Introduction To the Courses

Reliabilty Engineering

Introduction

This course covers Reliability Engineering Theory and Practical Examples. 

Course Objectives
  • Master the basic concepts associated with probability models.
  • Be able to translate models described in words to mathematical ones.
  • Understand probability models from empirical data.
  • Obtain some familiarity with the range of applications to complex systems. 
Student Outcomes
  • Basic Concept of Reliability Engineering

Probabilistic Risk Assessment (PRA) (Basic, Intermdediate, Advanced, and External)

Introduction

This course covers full scope of PRA methodology and Practical Examples. 

Course Objectives
  • Master the basic concepts of risk associated with PRA
  • Be able to develop fault tree models described in design documents
  • Understand and interpret PRA results.
  • Obtain insights from PRA  
  • Understand quantification process of event trees and fault trees using software
Student Outcomes
  • Basic concept of risk of NPPs and Technique to perform and undetstand PRA, correctly

Basic PRA

Introduction

This course covers the basics of PRA for further study about PRA.

Course Objectives
  • Understand concepts of risk and evolution of risk-informed approaches. 
  • Be able to understand PSA process. 
  • Understand the results and insights from PSA. 
  • Be able to explain the differences between deterministic and probabilistic approaches in safety. 
  • Obtain some familiarity with the range of risk-informed applications. 
  • Learn how to construct PSA model. 
  • Develop a solid understanding of the role of realism in PSA. 
Student Outcomes
  • Knowledge for development of PRA model Using PRA software

Introduction

This courses cover some simple example of PRA as well as special topics in PRA such as HRA, seismic PRA, etc.

Course Objectives
  • Risk Quantification
  • Risk Acceptacne
  • HRA
  • CCF
  • Event Tree and Fault Tree
Student Outcomes
  • Practical knowledge and experiences of PRA using PRA software
Home Outcomes

Publications, Projects and Awards

  • NSTAR-20NS42-41, Development of system analysis model for full power operation of Shin-Kori units 3&4 and 5&6, and mid-loop operation of Shin-Kori units 1&2 seismic PSA, Nuclear Safety and Security Commission, 2020.
  • NSTAR-19NS42-96, Development of system analysis model for Shin-Kori units 1&2 and Kori units 3&4 seismic PSA, Nuclear Safety and Security Commission, 2020.
  • NSTAR-19NS42-91, A Study on System Modeling of Seismic PSA to Prevent Overestimation of Seismic CDF Nuclear Safety and Security Commission, 2019.
  • NSTAR-19NS42-42, A Study on the Approach for Seismic PSA Modeling and Quantification, Nuclear Safety and Security Commission, 2019.
  • NSTAR-18NS21-28, Review of Multi-unit Risk Issues and Case Study of Korean Multi-unit Events, Nuclear Safety and Security Commission, 2018.
  • NSTAR-18NS11-29, Review of Current Seismic PSA Quantification Method and Improvement for Multi-unit Seismic Risk Quantification, Nuclear Safety and Security Commission, 2018.
  • Hak Kyu Lim and Jong-hoon Park, Effects of house load operation on PSA based on operational experiences in Korea, Nuclear Engineering and Technology, Volume 52, Issue 12, December 2020, Pages 2812-2820.
  • Hak Kyu Lim, A Study of System Analysis Method for Seismic PSA of Nuclear Power Plants, Journal of the Korean Society of Safety, Vol. 34, No. 5, October 2019, pp. 159-166
  • Hak Kyu Lim, A Study on the Operational Events of Domestic Nuclear Power Plants for Multi-unit Risk Journal of the Korean Society of Safety, Vol. 34, No. 5, October 2019, pp. 167-174

Projects

 
Home Galleries

Galleries

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