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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Implementation of a new empirical model of steam condensation for the passive containment cooling system into MARS-KS code: Application to containment transient analysis
Nuclear Engineering and Technology
2021 .10
Crash analysis of military aircraft on nuclear containment
Structural engineering and mechanics : An international journal
2015 .01
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
Performance evaluation of an improved pool scrubbing system for thermally-induced steam generator tube rupture accident in OPR1000
Nuclear Engineering and Technology
2024 .04
Investigation on damage assessment of fiber-reinforced prestressed concrete containment under temperature and subsequent internal pressure
Nuclear Engineering and Technology
2023 .06
Simplified Nonlinear FE Model for Reactor Containment Building
대한토목학회 학술대회
2020 .10
Simulation of Containment Pressurization in a Large Break-Loss of Coolant Accident Using Single-Cell and Multicell Models and CONTAIN Code
Nuclear Engineering and Technology
2016 .01
Crash analysis of military aircraft on nuclear containment
Structural Engineering and Mechanics, An Int'l Journal
2015 .01
Parametric analyses for the design of a closed-loop passive containment cooling system
Nuclear Engineering and Technology
2021 .04
P X – An Innovative Safety Concept for an Unmanned Reactor
Nuclear Engineering and Technology
2016 .01
Proposal and Analysis of Hydrogen Mitigation System Guiding Hydrogen in Containment Building
Journal of Advanced Marine Engineering and Technology (JAMET)
2015 .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
ATLAS 중형냉각재상실사고 모의실험 해석을 통한 SPACE 코드 예측능력 평가
한국유체기계학회 논문집
2023 .08
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
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
Dismantling Process Development of the Containment Building of Nuclear Power Plant
한국방사성폐기물학회 학술대회
2018 .01
고속 카메라를 이용한 수조 내부 스파저에서의 직접접촉응축 가시화 연구
대한기계학회 춘추학술대회
2018 .12
Experimental assessment of thermal radiation effects on containment atmospheres with varying steam content
Nuclear Engineering and Technology
2022 .11
Feasibility Study of Beta Detector for Small Leak Detection inside the Reactor Containment
방사선방어학회지
2018 .01
의류관리기에서 스팀 분사 시간이 히트펌프 사이클에 미치는 영향에 대한 실험적 연구
대한설비공학회 학술발표대회논문집
2022 .06
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