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Showing results 1 to 20 of 30

Issue DateTitleAuthor(s)TypeView
2019-08Abnormality Diagnosis System for Nuclear Power Plants Using Multiple Gated Recurrent Unit AlgorithmsLee, Seung Jun; Kim, Jae MinMaster's thesis185
2011-02Corrosion Behaviors of Structural Materials in Liquid Gallium and Gallium Alloy Environments for Nuclear ApplicationKim, Ji Hyun; Shin, Sang HunMaster's thesis640
2018-08Design of High Density Spent Fuel Storage Rack Applying Burnup CreditLee, Deokjung; Jeong, SanggeolMaster's thesis392
2017-08Effect of Gd-alloyed Neutron Absorber on Thermal Performance of a Spent Fuel CaskSohn, Dong-Seong; Lee, Hee-JaeMaster's thesis389
2011-08Effects of phosphoric acid based rust converter on stainless steels for anti-corrosion applicationsKim, Ji Hyun; Park, Jeong SeokMaster's thesis899
2013-02Effects of SiC nanofluid on reflood heat transfer and hydrodynamic cavitation on its crud-like deposition for light water reactorsBang, In Cheol; Kim, Seong ManMaster's thesis1047
2014-02The Evaluation on the Environmental Radiation around the Nuclear Facilities in UlsanKim, Hee Reyoung; Yoo, Dong HanMaster's thesis874
2019-02EXPERIMENTAL STUDY OF CORROSION ON STRUCTURAL MATERIALS FOR PYROCHEMICAL PROCESS IN HIGH TEMPERATURE MOLTEN SALTS CONTAINING FISSION PRODUCTSKim, Hee Reyoung; Jeong, HyeonjunMaster's thesis219
2018-08Generation of Windowed Multipole Library for on-the-fly Doppler Broadening in UNIST In-house Monte Carlo CodeLee, Deokjung; Khassenov, AzamatMaster's thesis271
2015-02High Temperature Corrosion Test of a Zirconium alloySohn, Dong-Seong; Baek, Je-KyunMaster's thesis1059
2019-08Implementation and Verification of Three-Dimensional MOC Transient Solver in Whole-core Transport code STREAMLee, Deokjung; Nguyen, Khang Hoang NhatMaster's thesis174
2014-08Irradiation Growth Modeling of Zirconium in Nuclear ReactorsKim, Ji Hyun; Choi, Sang IlMaster's thesis741
2015-02Modeling of the Thermal Conductivity of U-Mo/Al Dispersion FuelSohn, Dong-Seong and Kim, Yeon Soo; Cho, Byoung JinMaster's thesis811
2018-08MULTI-SPECIES MULTI-PHYSICS MODELING AND VALIDATION OF HYDRODYNAMIC ELECTROCHEMICAL SYSTEM FOR USED NUCLEAR FUELKim, Hee Reyoung; Kang, DokyuMaster's thesis219
2019-08Neutron XS Library Generation of ENDF/B-VIII.0 for MOC code STREAM and Monte Carlo code MCSLee, Deokjung; Kim, KihoMaster's thesis176
2015-08New Burnable Absorber and Zirconium Reflector for Advanced PWRsLee, Deokjung; Choe, JiwonMaster's thesis839
2018-02ON-SITE LASER-INDUCED BREAKDOWN SPECTROSCOPY (LIBS) FOR POSTDETONATION NUCLEAR FORENSICS IN REAL TIMEKim, Hee Reyoung; Lee, ChankiMaster's thesis468
2012-08Prediction of Fuel Cladding Performance for Ultra-long Cycle Fast Reactor ApplicationKim, Ji Hyun; Jung, Ju AngMaster's thesis919
2019-02QUANTITATIVE SOFTWARE RELIABILITY ASSESSMENT OF THE SAFETY CRITICAL IN NUCLEAR REACTOR PROTECTION SYSTEMLee, Seung Jun; Seo, JeongilMaster's thesis172
2018-02Radiological Impact Assessment of the Korean Peninsula due to Foreign Nuclear AccidentKim, Heereyoung; Min, JaeseongMaster's thesis373
Showing results 1 to 20 of 30

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