사진

  • Scopus

Lee, Seung Jun (이승준)

Department
Department of Nuclear Engineering(원자력공학과)
Website
http://psa.unist.ac.kr/
Lab
Nuclear Safety Assessment and Plant HMI Evolution Lab. (원자력 안전성평가 및 HMI 혁신 연구실)
Research Keywords
원자력, 원자력발전소, 안전성평가, 인간기계연계, 인간신뢰도분석, 리스크정보활용, 운전원전지원시스템, Nuclear Safety Assessment, Nuclear Power Plant, Nuclear, Human reliability analysis, Risk-informed application, Autonomous system development, Human Machine Interface, HMI
Research Interests
Nuclear Power Plant Safety Assessment“How to assess the safety of a nuclear power plant?” “How safe is safe enough?”We are performing the researches to answer the questions and to make nuclear power plants safer. The risk assessment of nuclear power plants is crucial in plant designing, licensing, and various decision makings. To assess the plant safety more accurately, we are solving the emerging issues such as reliability of safety-critical digital systems, human reliability in digitalized environment, cyber security, dynamic risk assessment, and multi-unit risk assessment.
Plant Human Machine Interface (HMI) EvolutionHuman error is one of the major contributors in the nuclear power plant safety. Since a nuclear power plant is a large complex system with ten thousands of components, it is not easy to diagnose the current situation and to perform corrective actions quickly and accurately even for highly trained operators. To improve the plant safety by preventing human errors, we are developing an innovative plant HMI with high level automation systems using the artificial intelligence technology.
This table browses all dspace content
Issue DateTitleAuthor(s)TypeViewAltmetrics
2020-09Abnormality Diagnosis Model for Nuclear Power Plants Using Two-Stage Gated Recurrent UnitsKim, Jae Min; Lee, Gyumin; Lee, Changyong, et alARTICLE161 Abnormality Diagnosis Model for Nuclear Power Plants Using Two-Stage Gated Recurrent Units
2020-09External dose assessment for workers dismantling the bio-shield of a commercial power nuclear reactor: Case study of Kori-1, KoreaLee, ChoongWie; Lee, Donghyun; Kim, Hee Reyoung, et alARTICLE230 External dose assessment for workers dismantling the bio-shield of a commercial power nuclear reactor: Case study of Kori-1, Korea
2020-08Occupational internal exposure calculation during dismantling of bio-shield of Kori nuclear power plant unit#1Lee, ChoongWie; Lee, Donghyun; Kim, Hee Reyoung, et alARTICLE114 Occupational internal exposure calculation during dismantling of bio-shield of Kori nuclear power plant unit#1
2020-07Comparison of Multilayer Perceptron and Long Short-Term Memory for Plant Parameter Trend PredictionBae, Junyong; Ahn, Jeeyea; Lee, Seung JunARTICLE146 Comparison of Multilayer Perceptron and Long Short-Term Memory for Plant Parameter Trend Prediction
2020-07A quantitative assessment framework for cyber-attack scenarios on nuclear power plants using relative difficulty and consequencePark, Jong Woo; Lee, Seung JunARTICLE112 A quantitative assessment framework for cyber-attack scenarios on nuclear power plants using relative difficulty and consequence
2020-07Experimental approach to evaluate software reliability in hardware-software integrated environmentSeo, Jeongil; Kang, Hyun Gook; Lee, Eun-Chan, et alARTICLE50 Experimental approach to evaluate software reliability in hardware-software integrated environment
2020-06The effect of communication quality on team performance in digital main control room operationsKim, HyungJun; Kim, Seunghwan; Park, Jinkyun, et alARTICLE199 The effect of communication quality on team performance in digital main control room operations
2020-03Consistency Index-Based Sensor Fault Detection System for Nuclear Power Plant Emergency Situations Using an LSTM NetworkChoi, Jeonghun; Lee, Seung JunARTICLE92 Consistency Index-Based Sensor Fault Detection System for Nuclear Power Plant Emergency Situations Using an LSTM Network
2020-01Optimization of software development life cycle quality for NPP safety software based on a risk-cost modelLee, Sang Hun; Lee, Seung Jun; Koo, Seo Ryong, et alARTICLE179 Optimization of software development life cycle quality for NPP safety software based on a risk-cost model
2020-01Exhaustive testing of safety-critical software for reactor protection systemLee, Sang Hun; Lee, Seung Jun; Shin, Sung Min, et alARTICLE222 Exhaustive testing of safety-critical software for reactor protection system
2019-10Exhaustive test cases for the software reliability of safety-critical digital systems in nuclear power plantsCho, Jaehyun; Shin, Sung Min; Lee, Seung Jun, et alARTICLE261 Exhaustive test cases for the software reliability of safety-critical digital systems in nuclear power plants
2019-09Analysis of interface management tasks in a digital main control roomChoi, Jeonghun; Kim, Hyoungju; Jung, Wondea, et alARTICLE229 Analysis of interface management tasks in a digital main control room
2019-06Evaluation of effectiveness of fault-tolerant techniques in a digital instrumentation and control system with a fault injection experimentKim, Man Cheol; Seo, Jeongil; Jung, Wondea, et alARTICLE402 Evaluation of effectiveness of fault-tolerant techniques in a digital instrumentation and control system with a fault injection experiment
2019-04Safety Assessment Framework for Nuclear Power Plant Decommissioning WorkersKim, HyungJun; Lee, Donghyun; Lee, Choong Wie, et alARTICLE220 Safety Assessment Framework for Nuclear Power Plant Decommissioning Workers
2019-02Probabilistic safety assessment-based importance analysis of cyber-attacks on nuclear power plantsPark, Jong Woo; Lee, Seung JunARTICLE423 Probabilistic safety assessment-based importance analysis of cyber-attacks on nuclear power plants
2018-10Development of a Bayesian belief network model for software reliability quantification of digital protection systems in nuclear power plantsKang, Hyun Gook; Lee, Sang Hoon; Lee, Seung Jun, et alARTICLE686 Development of a Bayesian belief network model for software reliability quantification of digital protection systems in nuclear power plants
2018-10Bayesian Belief Network Model Quantification Using Distribution-Based Node Probability and Experienced Data Updates for Software Reliability AssessmentLee, Seung Jun; Lee, Sang Hun; Chu, Tsong-Lun, et alARTICLE269 Bayesian Belief Network Model Quantification Using Distribution-Based Node Probability and Experienced Data Updates for Software Reliability Assessment
2018-05Development of simulation-based testing environment for safety-critical softwareLee, Sang Hun; Lee, Seung Jun; Park, Jinkyun, et alARTICLE430 Development of simulation-based testing environment for safety-critical software
2017-05Fault-weighted quantification method of fault detection coverage through fault mode and effect analysis in digital I&C systemsCho, Jaehyun; Lee, Seung Jun; Jung, WondeaARTICLE457 Fault-weighted quantification method of fault detection coverage through fault mode and effect analysis in digital I&C systems
2016-08Reactor protection system software test-case selection based on input-profile considering concurrent events and uncertaintiesKhalaquzzaman, Mohamed; Lee, Seung Jun; Choi, Jaehyun Choi, et alARTICLE515 Reactor protection system software test-case selection based on input-profile considering concurrent events and uncertainties

MENU