Faculty Research Profile
Jaeyeong Park
학력
· 2014: Ph.D. in Nuclear Engineering, Seoul National University
· 2010: B.S. in Nuclear Engineering, Seoul National University
주요 경력
· 2015~2017: Senior Researcher, Korea Institute of Nuclear Safety
수상/학회/외부활동
· 한국원자력기술유공 과학기술정보통신부 표창 (2023)
핵연료주기 및 방사성폐기물 연구실
Fuel Cycle and Waste Laboratory
핵연료주기 및 방사성폐기물 연구실은 방사성 폐기물 및 사용 후 핵연료 문제에 대한 해결책을 찾기 위해 노력하고 있습니다. 우리 연구실의 관심 분야는 일반적으로 1) 방사성 폐기물 오염 제거, 2) 방사성 폐기물 처리, 3) 사용 후 핵연료 재활용, 4) 사용 후 핵연료 처리의 네 가지 주요 영역에 있습니다.
Fuel Cycle and Waste Lab (FCWL) endeavors to find out a solution for radioactive waste and spent nuclear fuel issues, arising from generation to disposal. Our lab interests lie generally in four major areas: 1) radioactive waste decontamination, 2) radioactive waste disposal, 3) spent nuclear fuel recycling, 4) spent nuclear fuel disposal.
Fuel Cycle and Waste Lab (FCWL) endeavors to find out a solution for radioactive waste and spent nuclear fuel issues, arising from generation to disposal. Our lab interests lie generally in four major areas: 1) radioactive waste decontamination, 2) radioactive waste disposal, 3) spent nuclear fuel recycling, 4) spent nuclear fuel disposal.
연구분야
Radioactive waste decontamination, Radioactive waste disposal, Spent nuclear fuel recycling, Spent nuclear fuel disposal
Radioactive waste decontamination, Radioactive waste disposal, Spent nuclear fuel recycling, Spent nuclear fuel disposal
연구주제
· 방사성 금속의 용융 염 기반 전기 화학적 오염 제거
Molten salt based electrochemical decontamination of radioactive metals
· 용융염 원자로 구조재료 부식 특성 및 부식 완화 기술 개발
Characterization and mitigation of corrosion of structural materials in a molten salt reactors
· 액체 금속 전극을 사용한 사용후핵연료 내 악티나이드 원소 고도분리
High order separation of actinide elements from spent nuclear fuel using liquid metal electrodes
· 방사성폐기물 처분시설 내 방사성 물질 및 기타 유해 물질의 화학적 안정성
Chemical behaviors of radionuclides and hazardous materials in radioactive waste repositories
· 사용후핵연료 처분시설 공학적 방벽 안전성 평가
Safety assessment of engineering barriers of spent nuclear fuel repository
· 방사성폐기물 재활용 및 처분으로 인한 방사선적 위험도 평가
Radiological risk assessment on radioactive waste disposal and recycling
· Molten salt based electrochemical decontamination of radioactive metals
· Characterization and mitigation of corrosion of structural materials in a molten salt reactors
· High order separation of actinide elements from spent nuclear fuel using liquid metal electrodes
· Chemical behaviors of radionuclides and hazardous materials in radioactive waste repositories
· Safety assessment of engineering barriers of spent nuclear fuel repository
· Radiological risk assessment on radioactive waste disposal and recycling
국가연구개발사업 기술 분류체계
국가과학기술표준분류
EG. 원자력 > EG06. 핵연료주기·방사성폐기물 관리기술
논문
· CORROSION SCIENCE/ Effects of NiCl2 and FeCl2 additives on the anodic dissolution behaviours of Inconel 600 in molten LiCl–KCl salts / Jeon,Younghwan; Hur, Jungho; Jeong, Gwan Yoon; Park, Jaeyeong / 2023-6
· NUCLEAR ENGINEERING AND TECHNOLOGY / Leachability of lead, cadmium, and antimony in cement solidified waste in a silo-type radioactive waste disposal facility environment/ Lee, Yulim; Byeon, Hyeongjin; Park, Jaeyeong/ 2023-8
· Tunnelling and Underground Space Technology / Structural stability of stacked disposal containers in silo-type low-and intermediate-level waste repository under weight of backfilling materials / Byeon, Hyeongjin; Park, Jaeyeong/ 2023-3
· International Journal of Energy Research / Zirconium metal recovery from irradiated radioactive zirconium alloy via chloride‐based electrorefining and thermal decomposition of ZrCl / Hur, Jungho; Jeon, Younghwan; Jeong, Gwan Yoon; Sohn, Sungjune; Choi, Sungyeol; Park, Jaeyeong / 2022-4
특허
· 지르코늄 회수 공정 및 폐 지르코늄 처리방법 / 10-2020-0189429
· 네오디뮴 회수 공정 및 네오디뮴 회수 장치 / 10-2538237