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가 나 다 라 마 바 사 아 자 차 카 타 파 하

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3D-printed heat pipe with advanced capillary wick structure for large-scale nuclear power plant applications File

Thesis Issue Date2024-02 View8

Design and modeling of the hydraulic control rod drive mechanism for passive in-core cooling system File File

Thesis Issue Date2019-02 View5

Design and Performance of Hybrid Control Rod For Passive IN-core Cooling System File File

Thesis Issue Date2017-08 View6

Development of relocation model of molten metallic fuel in core disruptive accident of sodium-cooled fast reactor File File

Thesis Issue Date2019-02 View5

Dry-out limit enhancement and optimal filling ratio determination in sodium heat pipes based on the overfilling effect File

Thesis Issue Date2024-02 View5

Effect of CRUD deposition on the sub-cooled nucleate boiling characteristics of fuel cladding in pressurized water reactor operating condition File

Thesis Issue Date2024-02 View5

Effects of Graphene and SiC Nanofluids on Critical Heat Flux and Quenching for Advanced Nuclear Reactors File File

Thesis Issue Date2013-11 View4

Effects of Surface Characteristics in Pool Boiling Critical Heat Flux Enhancement, and its Prediction Model File File

Thesis Issue Date2017-02 View7

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

Thesis Issue Date2015-08 View10

Investigation of acoustic characteristics in boiling phenomena and deep learning-based boiling monitoring system using acoustic signals File

Thesis Issue Date2024-02 View33

Phenomenological Study of Fuel Relocation Behavior and Formation of Debris Bed in Metal-fueled Sodium-cooled Fast Reactor File File

Thesis Issue Date2019-02 View10

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

Thesis Issue Date2018-08 View7

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 View9

Study on Natural Circulation of the Reactor Pool under RVACS Operation using Fluid to Fluid Model Simulating Experiment File File

Thesis Issue Date2020-08 View6

Study on the Multiphysics Modeling of Molten Salt Reactor Using Adjoint-based Sensitivity Analysis Method File File

Jeong, Yeong Shin

Thesis Issue Date2019-02 View5

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