Scholarworks@UNIST

UNIST Library

Browsing "NUE_Theses_Ph.D." by Title :

All A B C D E F G H I J K L M N O P Q R S T U V W X Y Z

가 나 다 라 마 바 사 아 자 차 카 타 파 하

Sort by: In order: Results/Page Etal:

Showing results 21 to 40 of 65

Development of Nodal Diffusion Code for VVER and HTGR analysis with Advanced Semi Analytic Nodal Method File File

Jang, Jaerim

Thesis Issue Date2023-08 View15

Development of Reactor Multiphysics framework to analyze the effect of crossflow and dynamic gHTC for Depletion and REA transient File File

Awais Zahur

Thesis Issue Date2023-08 View16

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

Moon, Sungbo

Thesis Issue Date2019-02 View8

Development of Ultra-long Cycle Small Modular Sodium-cooled Fast Reactor Core Concept File File

Tak, Taewoo

Thesis Issue Date2017-02 View16

Development of Zirconium Decontamination Process by Combining Molten Salt Electrolysis and Pyrolysis of Irradiated Zr-alloy Waste File File

Hur, Jungho

Thesis Issue Date2023-02 View17

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

Lee, Dong Hun

Thesis Issue Date2024-02 View23

Dynamic Radiation Safety Assessment of Workers During the Decommissioning of Radioactive Concrete File File

Lee, ChoongWieLee

Thesis Issue Date2021-02 View8

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

Kim, Ji Yong

Thesis Issue Date2024-02 View17

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 View21

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

Seo, Han

Thesis Issue Date2017-02 View17

Enhanced Accident Performance of Zirconium Alloy Cladding Tube by High-Temperature Preformed Oxide and Analysis of Preformed Oxide Microstructures File File

Lee, Cheol Min

Thesis Issue Date2018-08 View14

Enhancing the energy deposition model in STREAM with photon transport module File

Mai, Nhan Nguyen Trong

Thesis Issue Date2024-02 View34

Establishment and Application of Diamond Detector Analysis System File

Kong, Chidong

Thesis Issue Date2020-02 View9

Focusing Grade as a Measure for Graded Approaches to Safety Culture Management in the Nuclear Industry File

Ahn, Jeeyea

Thesis Issue Date2023-08 View55

Gadolinium added uranium mononitride fuels for light water reactor applications: fabrication and thermophysical property measurements File File

Kim, Gyeonghun

Thesis Issue Date2021-08 View10

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 View19

Gd and B Based Integral Neutron Absorber for Spent Fuel Transportation and Storage System File

Kim, Mi Jin

Thesis Issue Date2020-02 View9

In Situ YAlO3(Ce) Gamma Spectrometry System for Underwater Survey by Remotely Operated Vehicle File File

Lee, Chanki

Thesis Issue Date2022-02 View9

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 View18

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

Lim, Do Yeong

Thesis Issue Date2024-02 View62

<< < 1 2 3 4 > >>

RSS 1.0 RSS 2.0

UNIST | Library

Tel : 052-217-1404 / Email : scholarworks@unist.ac.kr

ScholarWorks@UNIST was established as an OAK Project for the National Library of Korea.