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Showing results 1 to 20 of 86

Issue DateTitleAuthor(s)TypeView
2020-11A convolutional neural network model for abnormality diagnosis in a nuclear power plantLee, Gyumin; Lee, Seung Jun; Lee, ChangyongARTICLE2
2020-11A Sensor Fault-Tolerant Accident Diagnosis SystemChoi, Jeonghun; Lee, Seung JunARTICLE36
2018-08A Study on Pre-Transition Corrosion Behavior of Zirconium Alloy in Simulated Primary Water Conditions of Nuclear Power PlantKim, Ji Hyun; Kim, TaehoDoctoral thesis264
2019-08A Study on Primary Water Stress Corrosion Cracking Behavior of Forged Alloy 600 in Nuclear Power PlantKim, Ji Hyun; Yoo, Seung ChangDoctoral thesis248
2020-09Abnormal state diagnosis model tolerant to noise in plant dataShin, Ji Hyeon; Kim, Jae Min; Lee, Seung JunARTICLE25
2019-08Abnormality Diagnosis System for Nuclear Power Plants Using Multiple Gated Recurrent Unit AlgorithmsLee, Seung Jun; Kim, Jae MinMaster's thesis185
2020-11-05Analysis of Helical-type Electromagnetic Pump for Lithium Charge StripperLee, GeunHyeong; Kim, Hee ReyoungCONFERENCE1
2020-08Analysis of VVER-1000 mock-up criticality experiments with nuclear data library ENDF/B-VIII.0 and Monte Carlo code MCSSetiawan, Fathurrahman; Lemaire, Matthieu; Lee, DeokjungARTICLE11
2011-02Corrosion Behaviors of Structural Materials in Liquid Gallium and Gallium Alloy Environments for Nuclear ApplicationKim, Ji Hyun; Shin, Sang HunMaster's thesis640
2020-12Deep learning-based procedure compliance check system for nuclear power plant emergency operationAhn, Jeeyea; Lee, Seung JunARTICLE43
2019-02Design and modeling of the hydraulic control rod drive mechanism for passive in-core cooling systemBang, In Cheol; Kim, In GukDoctoral thesis229
2017-08Design and Performance of Hybrid Control Rod For Passive IN-core Cooling SystemBang, In Cheol; Kim, Kyung MoDoctoral thesis476
2018-08Design of High Density Spent Fuel Storage Rack Applying Burnup CreditLee, Deokjung; Jeong, SanggeolMaster's thesis392
2020-11-12Design Proposal of Detection System for Gamma-ray Monitoring in Groundwater at Decommissioning SiteLee, Hyeonmin; Choi, Woo Nyun; Yoon, Seungbin; Kim, Hee ReyoungCONFERENCE1
2020-11Development of a multi-unit seismic conditional core damage probability model with uncertainty analysisHeo, Yunyeong; Lee, Seung JunARTICLE2
2019-02Development of a New Monte Carlo Code for High-Fidelity Power Reactor AnalysisLee, Deokjung; Lee, HyunsukDoctoral thesis267
2020-08Development of integrated nuclear electromagnetic pump for liquid metal cooled micro reactorKim, Hee Reyoung; Kwak, JaesikDoctoral thesis20
2020-06Development of mobile scanning system for effective in-situ spatial prediction of radioactive contamination at decommissioning sitesLee, Chanki; Park, Se-Won; Kim, Hee ReyoungARTICLE123
2019-02Development of relocation model of molten metallic fuel in core disruptive accident of sodium-cooled fast reactorBang, In Cheol; Moon, SungboDoctoral thesis178
2017-02Development of Ultra-long Cycle Small Modular Sodium-cooled Fast Reactor Core ConceptLee, Deokjung; Tak, TaewooDoctoral thesis618
Showing results 1 to 20 of 86