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Study on Heat Transfer behavior of High-Prandtl number fluid and its feasibility to Passive Heat Transport System File File

Seo, Seok Bin

Thesis Issue Date2018-08 View66
A Study on Pre-Transition Corrosion Behavior of Zirconium Alloy in Simulated Primary Water Conditions of Nuclear Power Plant File File

Kim, Taeho

Thesis Issue Date2018-08 View78
Irradiation Performance Modeling and PRIME Code Development for U-Mo Dispersion Fuel for Research Reactors File File

Jeong, Gwan Yoon

Thesis Issue Date2018-02 View97
Thermal Aging Effects on Fusion Boundary of Dissimilar Metal Weldments in Primary Coolant System of Nuclear Power Plant File File

Choi, Kyoung Joon

Thesis Issue Date2017-08 View97
Design and Performance of Hybrid Control Rod For Passive IN-core Cooling System File File

Kim, Kyung Mo

Thesis Issue Date2017-08 View128
Effects of Surface Characteristics in Pool Boiling Critical Heat Flux Enhancement, and its Prediction Model File File

Seo, Han

Thesis Issue Date2017-02 View83
Development of Ultra-long Cycle Small Modular Sodium-cooled Fast Reactor Core Concept File File

Tak, Taewoo

Thesis Issue Date2017-02 View95
Pin-based Pointwise Energy Slowing-down Method for Resonance Self-shielding Calculation File File

Choi, Sooyoung

Thesis Issue Date2017-02 View131
Gallium Passive Decay Heat Removal Systems Design and Evaluation for IVR-ERVCS of APR 1400 and PDHRS of UCFR-100 File File

Kang, Sarah

Thesis Issue Date2015-08 View97
Study on Hydrodynamic Instability-based Critical Heat Flux Enhancement Mechanism of Nanofluids and Liquid Metal Fin Concept File File

Park, Seong Dae

Thesis Issue Date2015-02 View89
A Study in Corrosion Behaviors of Ferritic/Martensitic Steels in Liquid Sodium Condition for Sodium-cooled Fast Reactor Application File File

Shin, Sang Hun

Thesis Issue Date2015-02 View111
In-situ Observation and Atomistic Modelling of Early Stage Oxidation / Corrosion Behavior of Nickel Base Alloys in Nuclear Power Plants File File

Kim, Jongjin

Thesis Issue Date2014-02 View124
Effects of Graphene and SiC Nanofluids on Critical Heat Flux and Quenching for Advanced Nuclear Reactors File File

Lee, Seung Won

Thesis Issue Date2013-11 View128
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