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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Comparisons of performance and operation characteristics for closed- and open-loop passive containment cooling system design
Nuclear Engineering and Technology
2021 .08
Optimal design of passive containment cooling system for innovative PWR
Nuclear Engineering and Technology
2017 .01
단순화된 피동 원자로건물 냉각계통 내 자연순환에 관한 수치적 연구
한국안전학회지
2018 .01
MARS-KS1.3을 이용한 피동원자로건물냉각계통 열수력 성능 예비분석
에너지공학
2015 .09
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
Crash analysis of military aircraft on nuclear containment
Structural engineering and mechanics : An international journal
2015 .01
GOTHIC을 이용한 원자로 건물 피동냉각계통 축소 모형 실험 장치 단일 튜브의 길이 방향 열전달 성능 분석
기술과 교육
2020 .03
Performance evaluation of an improved pool scrubbing system for thermally-induced steam generator tube rupture accident in OPR1000
Nuclear Engineering and Technology
2024 .04
PASTELS project - overall progress of the project on experimental and numerical activities on passive safety systems
Nuclear Engineering and Technology
2024 .03
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
고속 카메라를 이용한 수조 내부 스파저에서의 직접접촉응축 가시화 연구
대한기계학회 춘추학술대회
2018 .12
Crash analysis of military aircraft on nuclear containment
Structural Engineering and Mechanics, An Int'l Journal
2015 .01
Investigation on damage assessment of fiber-reinforced prestressed concrete containment under temperature and subsequent internal pressure
Nuclear Engineering and Technology
2023 .06
Dismantling Process Development of the Containment Building of Nuclear Power Plant
한국방사성폐기물학회 학술대회
2018 .01
원자로 건물 냉각을 위한 1차원 쉘앤튜브형 열교환기 최적설계
한국에너지학회 학술발표회
2018 .04
MARS-CUPID 연계코드를 이용한 피동원자로건물냉각계통 격납건물 내부 열수력거동 분석
한국전산유체공학회지
2022 .09
P X – An Innovative Safety Concept for an Unmanned Reactor
Nuclear Engineering and Technology
2016 .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
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
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