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Showing results 1 to 20 of 29

Issue DateTitleAuthor(s)TypeView
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 thesis250
2019-02Design and modeling of the hydraulic control rod drive mechanism for passive in-core cooling systemBang, In Cheol; Kim, In GukDoctoral thesis231
2017-08Design and Performance of Hybrid Control Rod For Passive IN-core Cooling SystemBang, In Cheol; Kim, Kyung MoDoctoral thesis477
2019-02Development of a New Monte Carlo Code for High-Fidelity Power Reactor AnalysisLee, Deokjung; Lee, HyunsukDoctoral thesis268
2020-08Development of integrated nuclear electromagnetic pump for liquid metal cooled micro reactorKim, Hee Reyoung; Kwak, JaesikDoctoral thesis20
2019-02Development of relocation model of molten metallic fuel in core disruptive accident of sodium-cooled fast reactorBang, In Cheol; Moon, SungboDoctoral thesis180
2017-02Development of Ultra-long Cycle Small Modular Sodium-cooled Fast Reactor Core ConceptLee, Deokjung; Tak, TaewooDoctoral thesis618
2013-11Effects of Graphene and SiC Nanofluids on Critical Heat Flux and Quenching for Advanced Nuclear ReactorsBang, In Cheol; Lee, Seung WonDoctoral thesis3452
2017-02Effects of Surface Characteristics in Pool Boiling Critical Heat Flux Enhancement, and its Prediction ModelBang, In Cheol; Seo, HanDoctoral thesis620
2018-08Enhanced Accident Performance of Zirconium Alloy Cladding Tube by High-Temperature Preformed Oxide and Analysis of Preformed Oxide MicrostructuresLee, Deokjung; Lee, Cheol MinDoctoral thesis261
2020-02Establishment and Application of Diamond Detector Analysis SystemLee, Deokjung; Kong, ChidongDoctoral thesis91
2015-08Gallium Passive Decay Heat Removal Systems Design and Evaluation for IVR-ERVCS of APR 1400 and PDHRS of UCFR-100Bang, In Cheol; Kang, SarahDoctoral thesis1022
2020-02Gd and B Based Integral Neutron Absorber for Spent Fuel Transportation and Storage SystemLee, Deokjung; Kim, Mi JinDoctoral thesis96
2014-02In-situ Observation and Atomistic Modelling of Early Stage Oxidation / Corrosion Behavior of Nickel Base Alloys in Nuclear Power PlantsKim, Ji Hyun; Kim, JongjinDoctoral thesis1072
2019-02Investigation of ZrN Non-Reactively Sputtered Diffusion Barrier Coating for U-Mo Dispersion FuelLee, Deokjung; Kim, Ji HyeonDoctoral thesis228
2018-02Irradiation Performance Modeling and PRIME Code Development for U-Mo Dispersion Fuel for Research ReactorsSohn, Dong-Seong; Jeong, Gwan YoonDoctoral thesis346
2018-08Measurements and Modeling of Thermal Conductivity of U-Mo/Al Dispersion Fuel for Research ReactorLee, Deokjung; Cho, Tae WonDoctoral thesis293
2019-02Modeling of Radiation-induced Dimensional Instability of Metals and Alloys in Nuclear Systems: Improved Understanding of the Stress and Alloying Elements Effects by Rate TheoryKim, Ji Hyun; Choi, Sang IlDoctoral thesis204
2019-02Novel Technologies for Mitigation of Flow Accelerated Corrosion of the Secondary Side of Pressurized Water ReactorsKim, Ji Hyun; Kim, SeunghyunDoctoral thesis241
Showing results 1 to 20 of 29