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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
2022-07Concept of an Intelligent Operator Support System for Initial Emergency Responses in Nuclear Power PlantsKang, Jung Sung; Lee, Seung JunARTICLE171 Concept of an Intelligent Operator Support System for Initial Emergency Responses in Nuclear Power Plants
2022-06Graded approach to determine the frequency and difficulty of safety culture attributes: The F-D matrixAhn, Jeeyea; Lee, Seung JunARTICLE243 Graded approach to determine the frequency and difficulty of safety culture attributes: The F-D matrix
2022-05Limit surface/states searching algorithm with a deep neural network and Monte Carlo dropout for nuclear power plant safety assessmentBae, Junyong; Park, Jong Woo; Lee, Seung JunARTICLE91 Limit surface/states searching algorithm with a deep neural network and Monte Carlo dropout for nuclear power plant safety assessment
2022-04Simulation Optimization Framework for Dynamic Probabilistic Safety AssessmentPark, Jong Woo; Lee, Seung JunARTICLE164 Simulation Optimization Framework for Dynamic Probabilistic Safety Assessment
2022-02Framework for the development of guidelines for nuclear power plant decommissioning workers based on risk informationHeo, Yunyeong; Lee, Choongwie; Kim, Hee Reyoung, et alARTICLE195 Framework for the development of guidelines for nuclear power plant decommissioning workers based on risk information
2021-12Real-time prediction of nuclear power plant parameter trends following operator actionsBae, Junyong; Kim, Geunhee; Lee, Seung JunARTICLE226 Real-time prediction of nuclear power plant parameter trends following operator actions
2021-04Abnormal state diagnosis model tolerant to noise in plant dataShin, Ji Hyeon; Kim, Jae Min; Lee, Seung JunARTICLE252 Abnormal state diagnosis model tolerant to noise in plant data
2021-03Development of a multi-unit seismic conditional core damage probability model with uncertainty analysisHeo, Yunyeong; Lee, Seung JunARTICLE219 Development of a multi-unit seismic conditional core damage probability model with uncertainty analysis
2021-02A convolutional neural network model for abnormality diagnosis in a nuclear power plantLee, Gyumin; Lee, Seung Jun; Lee, ChangyongARTICLE296 A convolutional neural network model for abnormality diagnosis in a nuclear power plant
2020-12Deep learning-based procedure compliance check system for nuclear power plant emergency operationAhn, Jeeyea; Lee, Seung JunARTICLE317 Deep learning-based procedure compliance check system for nuclear power plant emergency operation
2020-11A Sensor Fault-Tolerant Accident Diagnosis SystemChoi, Jeonghun; Lee, Seung JunARTICLE251 A Sensor Fault-Tolerant Accident Diagnosis System
2020-09Abnormality Diagnosis Model for Nuclear Power Plants Using Two-Stage Gated Recurrent UnitsKim, Jae Min; Lee, Gyumin; Lee, Changyong, et alARTICLE486 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 alARTICLE551 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 alARTICLE464 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 JunARTICLE358 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 JunARTICLE373 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 alARTICLE231 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 alARTICLE482 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 JunARTICLE335 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 alARTICLE386 Optimization of software development life cycle quality for NPP safety software based on a risk-cost model

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