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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Assessment of TRACE code for modeling of passive safety system during long transient SBO via PKL/SACO facility
Nuclear Engineering and Technology
2024 .08
Parametric analyses for the design of a closed-loop passive containment cooling system
Nuclear Engineering and Technology
2021 .04
단순화된 피동 원자로건물 냉각계통 내 자연순환에 관한 수치적 연구
한국안전학회지
2018 .01
Experimental investigation of two-phase natural circulation loop as passive containment cooling system
Nuclear Engineering and Technology
2021 .12
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
The concept of the innovative power reactor
Nuclear Engineering and Technology
2017 .01
Comparative study of CFD and 3D thermal-hydraulic system codes in predicting natural convection and thermal stratification phenomena in an experimental facility
Nuclear Engineering and Technology
2023 .04
Integral effect test for steam line break with coupling reactor coolant system and containment using ATLAS-CUBE facility
Nuclear Engineering and Technology
2021 .08
Comparisons of performance and operation characteristics for closed- and open-loop passive containment cooling system design
Nuclear Engineering and Technology
2021 .08
Multi-scale simulation of wall fi lm condensation in the presence of non-condensable gases using heat structure-coupled CFD and system analysis codes
Nuclear Engineering and Technology
2021 .08
피동안전주입계통 열수력현상에 대한 실험적 연구
대한기계학회 춘추학술대회
2016 .12
P X – An Innovative Safety Concept for an Unmanned Reactor
Nuclear Engineering and Technology
2016 .01
고속 카메라를 이용한 수조 내부 스파저에서의 직접접촉응축 가시화 연구
대한기계학회 춘추학술대회
2018 .12
Performance analysis of the passive safety features of iPOWER under Fukushima-like accident conditions
Nuclear Engineering and Technology
2019 .01
Investigation of Characteristics of Passive Heat Removal System Based on the Assembled Heat Transfer Tube
Nuclear Engineering and Technology
2016 .01
Application of Chernoff bound to passive system reliability evaluation for probabilistic safety assessment of nuclear power plants
Nuclear Engineering and Technology
2022 .08
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
Optimal design of passive containment cooling system for innovative PWR
Nuclear Engineering and Technology
2017 .01
일체형 원자로의 공랭식 열교환기 개념 연구
한국유체기계학회 논문집
2016 .04
Thermal-hydraulic 0D/3D coupling in OpenFOAM: Validation and application in nuclear installations
Nuclear Engineering and Technology
2023 .05
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