Experience

Korea Institute of Nuclear Safety

• 1 - 100 Employee

• Research Project Manager and Nuclear Safety Expert

  • Nov 2020 - Present

  - Responsible for planning and managing the long-term national nuclear safety research project titled “Study on Validation of the Consolidated Safety Analysis Platform for Applications of Enhanced Safety Criteria and New Nuclear Fuels”. This project was launched in February 2021.- As a long-term goal, this research project aims to develop a suitable code suite with multi-physics feature for conducting the safety analysis for design basis accidents such as LOCA (Loss of Coolant Accident) and RIA (Reactivity Insertion Accident) under the strengthened regulatory requirements coping high burn-up effects. As a short-term goal, this project scope includes the development of the regulatory analysis method for ATF (Accident Tolerance Fuel) and Passive Safety System of SMRs (Small Modular Reactors) performance evaluation.- Responsible for review of reactor core thermal-hydraulic design and inspections on fuel integrity, fuel reloading and reactor coolant system flow test.• Standard Design Certificate Application Review (SMART100 – integral type SMR with passive safety features)• Accident Analysis at Aged Condition Review (CANDU)• Reload Transition Safety Report Review (HIPER16)• Core Thermal-Hydraulic Design Code Review (SLTHEN for Sodium cooled Fast Reactor)• Periodic Safety Review (Westinghouse type)



OECD Nuclear Energy Agency

• France
• International Affairs
• 1 - 100 Employee

• Nuclear Safety Specialist

  • Oct 2017 - Oct 2020

  - Technical Secretariat of Working Group on Regulation of New Reactors (WGRNR) under OECD/NEA/Committee on Nuclear Regulation Activities (OECD/NEA/CNRA)• Implemented the successful transfer of ConEx (OECD/NEA) database to the IRS (IAEA)- Technical Secretariat of Working Group on Electrical Power Systems (WGELEC) under OECD/NEA/Committee on the Safety of Nuclear Installations (OECD/NEA/CSNI)• Organized Joint NEA-IAEA meeting on electrical power systems”¹ (December 2019)- Technical Secretariat of APR1400 Working Group under Multinational Design Evaluation Program (MDEP)• Supported KINS, FANR and USNRC for APR1400 reactor design review¹ I also contributed to organizing another NEA-IAEA joint technical workshop, “Current Implementation Status of Measures to Manage Open Phase Conditions in Electrical Power Systems of Nuclear Power Plants”, October 2020



Korea Institute of Nuclear Safety

• 1 - 100 Employee

• Nuclear Safety Expert

  • Apr 2014 - Sep 2017

  - Reviewer on Core Thermal-Hydraulic Design (SAR 4.4)• New Fuel Design Review (HIPER16, HIPER17, 37M for CANDU)• Critical Heat Flux Correlation Review (KCE-1M, KNF-H, KNF-X, 37M for CANDU)• Core Thermal Design Methodology Review (Statistical Analysis of DNBR Limit; SADL)• New System/Containment Analysis Codes Review (SPACE, CAP)• Non-LOCA Safety Analysis Methodology Review (with SPACE)• Reactivity Insertion Accident Safety Analysis Methodology Review• Periodic Safety Review• Reload Safety Evaluation• Research Reactor Construction Application Review (Ki-Jang Research Reactor)• Regional Overpower Protection System Review (CANDU)• Etc. (Power uprate, Steam generator replacement, Prevention of reactor trip by single control rod drop, Improved Technical Specification application)

• Resident Inspector of Nuclear Power Plant

  • Apr 2012 - Mar 2014

  - Resident Inspector of Uljin Nuclear Power Plant Site

• Nuclear Safety Expert and Principal Researcher

  • Sep 2000 - Mar 2012

  - Research Project Manager (June 2007 – March 2012)• Resolution of Sump Clogging Issue (Expert member for SPIRT: SumP Issue Resolution Team) (GSI-191)• Expert panel for PIRT for APR+ reactor (Passive Auxiliary Feedwater System)• Benchmarking study on Safety Standards (in compliance with MDEP)¹ • Development of Safety Margin Quantification Methodology based on OECD/NEA-SMAP and SM2A² • International Collaborative Standard Problem on Natural Circulation of Integral Reactor (IAEA)³ • Thermal-Hydraulic System Code Improvement for Passive Heat Removal System (MARS-KS)¹ Benchmark study on codes/standards and regulatory requirements among Korea, the US and the IAEA regulations with an aim to develop universal codes/standards and regulatory requirements acceptable under MDEP framework.² Joined an OECD/NEA research program for safety margin quantification study called “SMAP” in 2007 and contributed to the development of safety margin quantification method based on PSA. The result of that project was summarized in the report, "Safety Margins Acton Plan-Final Report, NEA/CSNI/R(2007)9." I also joined the follow-up research program called “SM2A” in 2009.³ Conduct accident analysis over MASLWER experimental facility with MARK-KS TH code including input deck development. (2010-2013)- Participant in Regulatory Research Program (March 2005 – May 2007)• In Service Test Inspection Guide• Check Valve Conditional Monitoring Program• Power Uprate- Reviewer on Safety Related Systems/On-site Inspector on Safety Related Systems for Operating and Under-construction Reactors (September 2000 – February 2005)• Motor-Operated Valves and Air-Operated Valves Evaluation Program Review• Safety Related Systems Review (Component Cooling Water, Circulation Water, Spent Fuel Pool Cooling, Emergency Core Cooling etc.)



Chungnam National University

• South Korea
• Higher Education
• 300 - 400 Employee

• University Lecturer

  • Sep 2000 - Feb 2001

  Delivering a class on "turbulence modeling" for graduate school in aerospace engineering department Delivering a class on "turbulence modeling" for graduate school in aerospace engineering department



Korea Atomic Energy Research Institute

• Postdoctoral Research Fellow

  • Apr 1999 - Oct 2000

  - Conducting Velocity Measurement Experiments for Sub-channel Fluid Flow with Hot-wire Anemometer- Development of In-house 2D Elliptic Code for Sub-channel Fluid Flow Analysis - Conducting Velocity Measurement Experiments for Sub-channel Fluid Flow with Hot-wire Anemometer- Development of In-house 2D Elliptic Code for Sub-channel Fluid Flow Analysis