• Design Verification Reports for Spent Fuel Pool Cooling & Cleanup System• Design Verification Reports for Reactor Coolant System (RCS) Auxiliary System• Consulting for Fire Protection System of the Sodium-Cooled Fast Reactor (SFR)• Consulting for Steam Generator Startup System of the Sodium-Cooled Fast Reactor (SFR)

• Detail Design of Seismic Monitoring system (SMS) for commercial power plant• Prepared or reviewed design documents and drawings such as design requirements, design descriptions, technical specifications, component specifications, test procedures, address table, general arrangement drawings, detail drawings, bills of materials, etc.• Concept Design for new development power plant

Performed and developed the uncertainty calculations of safety-related instrumentations. Performed and directed the verification and validation of the NuScale developed sub-channel analysis software as parts of the DCD submittal activities.Developed the reactor protection system (RPS) integrated logic for the unique NuScale reactor module design. Performed modeling and analysis of two-phase flow phenomena for the NuScale power plant unique helical coil steam generators.Performed analysis of boundary layer flow and heat transfer (Critical Heat Flux Correlation), as part of DCD submittal activities. Applied mathematical and numerical models for simulation of the system and core thermal-hydraulics for the unique NuScale reactor module design. Performed modeling, and the associated documentation, pertains to of neutron transport calculations, on variety of computer platforms for core physics, thermal-hydraulic, and shielding applications. Performed dimensional scaling analyses of the NuScale reactor module system.Design and development of NuScale Power plant Simulator

Prepared or reviewed the CPCS System Description, Design Specification, Interface Requirements, Design Data, System Design Requirements, Design Description, Test Procedure Documents etc.Carry out the Upgrading Digital I&C equipment and Computer System for PWR (Westinghouse).Prepared the Safety Analysis Report and dealt with licensing issues raised in body questions for CPCS.Supported the field commissioning and testing for CPCS (KSNP, Westinghouse PWR ).Participated in Human Machine Interface design for CPCS of KNGR.Participated in Software and Hardware development for CPCS prototype of KNGR.Digital Research Protection System Lab, National Research Lab.

1991.3.- 1996. 12. Junior Researcher, Korea Atomic Energy Research Institute (KAERI), KoreaCarried out design work of PWR Steam Generator Level Control System and Pressurizer Pressure Control System Carried out CANDU design work for Reactor Coolant Pump (RCP) Vibration Control System, Heavy Water Management (D2O) system, Nuclear Instrument System Wolsong #2, 3 & 4Prepared or reviewed CANDU design documents and drawings

Performed work of CANDU Reactor Coolant Pump (RCP) Vibration Monitoring System & D2O Management system Carried out conceptual design and detail design of D2O Management I&C systemsPrepared or reviewed design documents and drawings such as design requirements, design descriptions, technical specifications, component specifications, calibration procedures, elementary drawings, general arrangement drawings, detail drawings, bills of materials, etc.