지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
이용수
등록된 정보가 없습니다.
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Experimental study on hydrogen behavior and possible risk with different injection conditions in local compartment
Nuclear Engineering and Technology
2020 .08
Numerical analysis on in-core ignition and subsequent flame propagation to containment in OPR1000 under loss of coolant accident
Nuclear Engineering and Technology
2022 .08
CURRENT RESEARCH AND DEVELOPMENT ACTIVITIES ON FISSION PRODUCTS AND HYDROGEN RISK AFTER THE ACCIDENT AT FUKUSHIMA DAIICHI NUCLEAR POWER STATION
Nuclear Engineering and Technology
2015 .01
Proposal and Analysis of Hydrogen Mitigation System Guiding Hydrogen in Containment Building
Journal of Advanced Marine Engineering and Technology (JAMET)
2015 .06
해외 사례를 통한 수소혼입이 가스시설에 미치는 영향 연구
한국가스학회 학술대회논문집
2022 .05
Preliminary numerical study on hydrogen distribution characteristics in the process that flow regime transits from jet to buoyancy plume in time and space
Nuclear Engineering and Technology
2019 .01
PREDICTION OF HYDROGEN CONCENTRATION IN CONTAINMENT DURING SEVERE ACCIDENTS USING FUZZY NEURAL NETWORK
Nuclear Engineering and Technology
2015 .01
Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor
Nuclear Engineering and Technology
2016 .01
EXPERIMENTAL INVESTIGATIONS RELEVANT FOR HYDROGEN AND FISSION PRODUCT ISSUES RAISED BY THE FUKUSHIMA ACCIDENT
Nuclear Engineering and Technology
2015 .01
Integral effect test for steam line break with coupling reactor coolant system and containment using ATLAS-CUBE facility
Nuclear Engineering and Technology
2021 .08
Assessment of turbulent heat flux models for URANS simulations of turbulent buoyant flows in ROCOM tests
Nuclear Engineering and Technology
2022 .11
Contribution of Production and Loss Terms of Fission Products on In-containment Activity under Severe Accident Condition for VVER-1000
Nuclear Engineering and Technology
2019 .01
Modeling and Simulation of Temperature Behavior in Hydrogen Vessel during Refueling
한국가스학회 학술대회논문집
2020 .10
액체 수소 생산을 위한 예냉 시스템의 수소 가스 예냉 온도 및 열 교환기 면적에 관한 연구
한국수소및신에너지학회논문집
2024 .06
Analysis of heat-loss mechanisms with various gases associated with the surface emissivity of a metal containment vessel in a water-cooled small modular reactor
Nuclear Engineering and Technology
2024 .08
OVERVIEW ON HYDROGEN RISK RESEARCH AND DEVELOPMENT ACTIVITIES: METHODOLOGY AND OPEN ISSUES
Nuclear Engineering and Technology
2015 .01
Cross flow Micro-mix 방식을 이용한 수소 가스터빈 연소기 연소특성에 대한 수치해석적 연구
한국연소학회지
2019 .09
DEVELOPMENT OF A HYDROGEN DISPERSION MODEL USING CUPID CODE
한국전산유체공학회지
2019 .06
Experimental assessment of thermal radiation effects on containment atmospheres with varying steam content
Nuclear Engineering and Technology
2022 .11
Research on mechanism of gas leakage in microchannels of steel containment vessels for nuclear power plants
Nuclear Engineering and Technology
2024 .08
0