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  • Scopus

Lee, Seung Jun (이승준)

Department
School of Mechanical, Aerospace and Nuclear Engineering(기계항공및원자력공학부)
Research Interests
Probabilistic Safety Assessment, Digital I&C System Reliability, Human Reliability Analysis
Lab
Risk Assessment and Risk-Informed Application
Website
http://psa.unist.ac.kr
This table browses all dspace content
Issue DateTitleAuthor(s)TypeViewAltmetrics
2020-02External 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 alARTICLE11 External dose assessment for workers dismantling the bio-shield of a commercial power nuclear reactor: Case study of Kori-1, Korea
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 alARTICLE111 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 alARTICLE140 Exhaustive testing of safety-critical software for reactor protection system
2020Abnormality Diagnosis Model for Nuclear Power Plants Using Two-Stage Gated Recurrent UnitsKim, Jae Min; Lee, Gyumin; Lee, Changyong, et alARTICLE43 Abnormality Diagnosis Model for Nuclear Power Plants Using Two-Stage Gated Recurrent Units
2019-12Comparison of Multilayer Perceptron and Long Short-Term Memory for Plant Parameter Trend PredictionBae, Junyong; Ahn, Jeeyea; Lee, Seung JunARTICLE73 Comparison of Multilayer Perceptron and Long Short-Term Memory for Plant Parameter Trend Prediction
2019-11The effect of communication quality on team performance in digital main control room operationsKim, HyungJun; Kim, Seunghwan; Park, Jinkyun, et alARTICLE89 The effect of communication quality on team performance in digital main control room operations
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 alARTICLE185 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 alARTICLE148 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 alARTICLE318 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 alARTICLE137 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 JunARTICLE328 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 alARTICLE586 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 alARTICLE204 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 alARTICLE340 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, WondeaARTICLE376 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 alARTICLE432 Reactor protection system software test-case selection based on input-profile considering concurrent events and uncertainties
2016-01PSA model with consideration of the effect of fault-tolerant techniques in digital I&C systemsLee, Seung Jun; Jung, Wondea; Yang, Joon-EonARTICLE488 PSA model with consideration of the effect of fault-tolerant techniques in digital I&C systems
2015-12Reliability modeling of safety-critical network communication in a digitalized nuclear power plantLee, Sang Hun; Kim, Hee Eun; Son, Kwang Seop, et alARTICLE275 Reliability modeling of safety-critical network communication in a digitalized nuclear power plant
2014-12Estimation of reactor protection system software failure probability considering undetected faultsKhalaquzzaman, Mohamed; Lee, Seung Jun; Kim, Man Cheol, et alARTICLE172 Estimation of reactor protection system software failure probability considering undetected faults
2014-11A Guideline to HRA Data Collection from SimulationsPark, Jinkyun; Choi, Sunyong; Kim, Seung Hwan, et alARTICLE135

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