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Crash analysis of military aircraft on nuclear containment
Structural engineering and mechanics : An international journal
2015 .01
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
Parametric analyses for the design of a closed-loop passive containment cooling system
Nuclear Engineering and Technology
2021 .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
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
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
Investigation on damage assessment of fiber-reinforced prestressed concrete containment under temperature and subsequent internal pressure
Nuclear Engineering and Technology
2023 .06
Crash analysis of military aircraft on nuclear containment
Structural Engineering and Mechanics, An Int'l Journal
2015 .01
고속 카메라를 이용한 수조 내부 스파저에서의 직접접촉응축 가시화 연구
대한기계학회 춘추학술대회
2018 .12
Optimal design of passive containment cooling system for innovative PWR
Nuclear Engineering and Technology
2017 .01
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
Feasibility study of a dedicated nuclear desalination system: Low-pressure Inherent heat sink Nuclear Desalination plant (LIND)
Nuclear Engineering and Technology
2015 .04
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
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
Nuclear Engineering and Technology
2020 .01
Dismantling Process Development of the Containment Building of Nuclear Power Plant
한국방사성폐기물학회 학술대회
2018 .01
The concept of the innovative power reactor
Nuclear Engineering and Technology
2017 .01
Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea
Nuclear Engineering and Technology
2016 .01
일체형 원자로의 공랭식 열교환기 개념 연구
한국유체기계학회 논문집
2016 .04
Conceptual design of a MW heat pipe reactor
Nuclear Engineering and Technology
2024 .03
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