Scholarworks@UNIST

UNIST Library
Search

김지현
Kim, Ji Hyun

김지현

Department of Nuclear Engineering(원자력공학과)

  • UNIST Nuclear Innovative Materials Lab.
  • Website
Research Interests
Nuclear Materials;Nuclear Energy Engineering;원전재료;원자력재료;원자력소재;원자력에너지공학
Lab Description
The UNIMAT is pursuing the technology development of key solutions to current and future materials challenges in the nuclear energy system based on fundamental and comprehensive understanding in various academic disciplines including nuclear, mechanical, and materials science and engineering.
Research Keywords and Topics- Materials in operating nuclear power plant (structural material, cladding, pipe, non-metal)- Materials in operating next generation nuclear power plant (Accident-tolerated cladding, Irradiation effect, Material degradation in liquid metal coolant)- Atomistic behavior of material (Experiments and simulations in atomistic scale)
Researcher ID Research Gate ORCiD Scopus Google Scholar
Previous
Design and construction of fluid-to-fluid scaled-down small modular reactor platform: As a testbed for the nuclear-based hydrogen production File File

Kim, Ji Yong , Yoo, Seung Chang , Seo, Joo Hyung , Kim, Ji Hyun , Bang, In Cheol

Article Issue Date2024-03 View3
Effects of Cr and Mo contents on the flow-accelerated corrosion behavior of low alloy steels in the secondary side of pressurized water reactors File

Kim, Seunghyun , Kim, Gidong , Song, Sang-Woo , Kim, Ji Hyun

Article Issue Date2023-11 View17
Robust 2D layered MXene matrix-boron carbide hybrid films for neutron radiation shielding File File

Han, Ju-Hyoung , Seok, Shi-Hyun , Jin, Young Ho , Park, Jaeeun , Lee, Yunju , Yeo, Haeng Un , Back, Jong-Ho , Sim, Yeoseon , Chae, Yujin , Wang, Jaewon , et al

Article Issue Date2023-10 View12
Effects of yttrium on the oxidation behavior of Fe13Cr6AlY alloys under 1200 & DEG;C steam File

Kim, Sungyu , Lee, Chang-Hoon , Kim, Taeyong , Jang, Jae Hoon , Moon, Joonho , Falaakh, Dayu Fajrul , Kim, Ji Hyun , Bahn, Chi Bum

Article Issue Date2023-10 View8
The DISNY facility for sub-cooled flow boiling performance analysis of CRUD deposited zirconium alloy cladding under pressurized water reactor condition: Design, construction, and operation File File

Kim, Ji Yong , Lee, Yunju , Kim, Ji Hyun , Bang, In Cheol

Article Issue Date2023-09 View11
Stability of Cr oxide formed on Fe-20Cr-2Si alloy in 1200 degrees C steam or oxygen File

Moon, Joonho , Kim, Sungyu , Short, Michael P. , Kim, Ji Hyun , Bahn, Chi Bum

Article Issue Date2023-08 View15
Fatigue residual useful life estimation of Ni-base alloy weld with time-series data File

Park, Jae Phil , Ham, Junhyuk , Kim, Ji Hyun , Oh, Young-Jin , Bahn, Chi Bum

Article Issue Date2023-05 View17
Statistical analysis of S-N type environmental fatigue data of Ni-base alloy welds using weibull distribution File File

Park, Jae Phil , Ham, Junhyuk , Mohanty, Subhasish , Falaakh, Dayu Fajrul , Kim, Ji Hyun , Bahn, Chi Bum

Article Issue Date2023-05 View15
High-temperature steam oxidation of (Ti, Mo)C-forming FeCrAlY alloy File

Kim, Sungyu , Lee, Chang-Hoon , Jang, Jae Hoon , Moon, Joonho , Kim, Ji Hyun , Bahn, Chi Bum

Article Issue Date2023-02 View18
Effects of heat and gamma radiation on the degradation behaviour of fluoroelastomer in a simulated severe accident environment File File

Song, Inyoung , Lee, Taehyun , Ryu, Kyungha , Kim, Yong Jin , Kim, Myung Sung , Park, Jong Won , Kim, Ji Hyun

Article Issue Date2022-12 View13
파울링된 피복관 표면의 가압 경수로 운전환경에서의 미포화 비등 열전달 성능평가를 위한 실험장치 구축 연구 File

김지용 , 이윤주 , 함준혁 , 김지현 , 방인철

Article Issue Date2022-10 View22
Effect of Steady-State Oxidation on Tensile Failure of Zircaloy Cladding File

Kim, Taeho , Choi, Kyoung Joon , Yoo, Seung Chang , Lee, Yunju , Kim, Ji Hyun

Article Issue Date2022-06 View17
Accelerated corrosion tests of Al-B4C neutron absorber used in spent nuclear fuel pool File

Jung, Yunsong , Lee, Yunju , Kim, Ji Hyun , Ahn, Sangjoon

Article Issue Date2021-08 View19
Effect of TiN Coating on the Fouling Behavior of Crud on Pressurized Water Reactor Fuel Cladding File

Ham, Junhyuk , Lee, Yunju , Yoo, Seung Chang , Short, Michael P. , Bahn, Chi Bum , Kim, Ji Hyun

Article Issue Date2021-06 View11
Development of probabilistic primary water stress corrosion cracking initiation model for alloy 182 welds considering thermal aging and cold work effects File File

Park, Jae Phil , Yoo, Seung Chang , Kim, Ji Hyun , Bahn, Chi Bum

Article Issue Date2021-06 View20
In-situ electrochemical study of zirconium alloy in high temperature hydrogenated Water conditions File

Kim, Taeho , Couet, Adrien , Kim, Seunghyun , Lee, Yunju , Yoo, Seung Chang , Kim, Ji Hyun

Article Issue Date2020-08 View13
Using rate theory to better understand the stress effect of irradiation creep in iron and its based alloy File

Choi, Sang Il , Banisalman, Mosab Jaser , Lee, Gyeong-Geun , Kwon, Junhyun , Yoon, Eisung , Kim, Ji Hyun

Article Issue Date2020-08 View14
비금속 소재 열화 거동에 대한 열 및 방사선 영향성 평가 File

이태현 , 송인영 , 류경하 , 백동천 , 박종원 , 김지현

Article Issue Date2019-12 View23
Soft X-ray study on electronic structure of passive oxide layer of carbon steel and low alloy steel in flow-accelerated corrosion environments of pressurized water reactors File

Kim, Seunghyun , Kim, Taeho , Lee, Yunju , Kim, Ji Hyun

Article Issue Date2019-10 View13
A Study on the Relationship between Electronic Structure and Corrosion Characteristics of Zirconium Alloy in High-temperature Hydrogenated Water File

Kim, Taeho , Kim, Seunghyun , Lee, Yunju , Kim, Namdong , Bahn, Chi Bun , Couet, Adrien , Kim, Ji Hyun

Article Issue Date2019-08 View12
1 2 3 4 5 >>

RSS 1.0 RSS 2.0

CONTACT US

UNIST | Library

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

Copyright (c) 2023 by UNIST LIBRARY. All rights reserved.

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