Advanced Reactor Lab
Advanced Reactor Lab
KAIST · Nuclear and Quantum Engineering
Professor
Prof. 장창희
Professor's page · publicationsAbout
KAIST 원자력및양자공학과 장창희 교수(Bently Chair Professor)의 원자로 및 고온 재료 연구실(NURMAT, Nuclear Reactor and High Temperature Materials Lab)이다. 차세대 원전용 고성능 스테인리스강 등 원자력 구조재료의 환경피로·고온증기 부식·중성자 조사 저항성, 응력부식균열 등을 합금 설계와 나노석출물 제어를 통해 연구한다.
Research keywords
Recent papers
- Low-cycle fatigue of Alloy 690 in high-temperature water containing NH3 – Enhancement of fatigue life compared to PWR waterCorrosion Science · Sep 1
- Corrosion and electrochemical response of 316L stainless steel in boron-free small modular reactor environments with KOH and NH3Nuclear Engineering and Design · Aug 13
From OpenAlex · papers whose author affiliation matches this university
Selected publications
- Phase stability and mechanical property of B2-Ni (Al, Fe) in a duplex Fe-Ni-Cr-Al alloy during aging 375 C to 475 CJournal of Materials Research and Technology · 2025
- A comparative study of thermal aging behavior of CF8M cast austenitic stainless steel and ER316L austenitic stainless steel weldJournal of Materials Research and Technology · 2025
- Corrosion and nodule oxide formation mechanism of Alloy 625 in high temperature CO2 environment with impuritiesCorrosion Science · 2025
- Effect of initial microstructure on irradiation induced microstructure evolution in delta-ferrite in an austenitic stainless steel weldJournal of Nuclear Materials · 2024
- The effect of microstructure of an advanced duplex stainless steel on the pitting corrosion and chloride-induced stress corrosion cracking resistanceCorrosion Science · 2024
- Accelerated Formation of Oxide Layers on Zircaloy-4 Utilizing Air Oxidation and Comparison with Water-Corroded Oxide LayersMaterials · 2023
Labs doing related research
Labs that recently published on topics this lab's recent papers share
Eun Seon Cho
KAIST · Chemical and Biomolecular Engineering
Flash Joule heating-driven reduced graphene oxide encapsulation of Mg-based alloys for high-performance and stable hydrogen storageNewJournal of Material Science and Technology · Oct 11Shared topic: Hydrogen embrittlement and corrosion behaviors in metals
Kim, Sangshik
Gyeongsang National University · Materials Science and Engineering
Microsegregation-induced corrosion fatigue behavior of a cast Mn-Cu alloy in 3.5 wt% NaCl solutionJournal of Materials Research and Technology · Sep 18Shared topic: Fatigue and fracture mechanics
Jae-Gil Jung
Jeonbuk National University · Materials Science and Engineering
Corrosion Behavior of Additively Manufactured Ti-6Al-4V Alloy Annealed at 650 °C in 3.5 wt% NaCl SolutionMetals and Materials International · Aug 24Shared topic: Hydrogen embrittlement and corrosion behaviors in metals
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- Nuclear Fuel LabRecruiting
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- Plasma Physics Lab
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Plasma Physics, Fusion Energy, Plasma Diagnostics
- Nuclear Safety Lab
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- Radiation Measurement Lab
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- Reactor Physics Lab
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Reactor Physics, Neutronics, Nuclear Design