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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Characteristics of debris resulting from simulated molten fuel coolant interactions in SFRS
Nuclear Engineering and Technology
2024 .01
A REVIEW OF INHERENT SAFETY CHARACTERISTICS OF METAL ALLOY SODIUM-COOLED FAST REACTOR FUEL AGAINST POSTULATED ACCIDENTS
Nuclear Engineering and Technology
2015 .04
금속연료 소듐냉각고속로 중대사고 고유안전특성 SAS4A/SASSYS-1 코드 전산해석
한국전산유체공학회지
2021 .03
A study on modeling of boiling heat transfer in core debris bed of SFR
Nuclear Engineering and Technology
2024 .09
Numerical simulation on jet breakup in the fuel-coolant interaction using smoothed particle hydrodynamics
Nuclear Engineering and Technology
2021 .10
연구용 원자로의 원자로 구조물 집합체 스트레이너에서의 압력강하 평가
대한기계학회 춘추학술대회
2018 .12
Development and validation of the lead-bismuth cooled reactor system code based on a fully implicit homogeneous flow model
Nuclear Engineering and Technology
2024 .04
Study on relocation behavior of debris bed by improved bottom gas-injection experimental method
Nuclear Engineering and Technology
2021 .01
Discharge header design inside a reactor pool for flow stability in a research reactor
Nuclear Engineering and Technology
2020 .10
Evaluating direct vessel injection accident-event progression of AP1000 and key figures of merit to support the design and development of water-cooled small modular reactors
Nuclear Engineering and Technology
2024 .06
Performance evaluation of the Floating Absorber for Safety at Transient (FAST) in the innovative Sodium-cooled Fast Reactor (iSFR) under a single control rod withdrawal accident
Nuclear Engineering and Technology
2020 .01
Dynamics and control of molten-salt breeder reactor
Nuclear Engineering and Technology
2017 .01
Study on bidirectional fluid-solid coupling characteristics of reactor coolant pump under steady-state condition
Nuclear Engineering and Technology
2019 .01
FAST (Floating Absorber for Safety at Transient) for the Improved Safety of Sodium-cooled Burner Fast Reactors
Nuclear Engineering and Technology
2021 .06
EXPERIMENTAL STUDY ON DEVELOPMENT OF EX-VESSEL DEBRIS BED WITH INCLINED BOTTOM SURFACE
대한기계학회 춘추학술대회
2020 .12
연구용 원자로 격자판에서의 온도분포 평가
대한기계학회 춘추학술대회
2017 .11
용융염원자로의 잔열제거를 위한 피동냉각계통 개념
대한기계학회 춘추학술대회
2021 .11
Electric power frequency and nuclear safety - Subsynchronous Resonance case study
Nuclear Engineering and Technology
2019 .01
APR1400 RCP(Reactor Coolant Pump) 디지털 트윈 모델 개발
대한기계학회 춘추학술대회
2022 .11
Enhancing the performance of a long-life modifi ed CANDLE fast reactor by using an enriched 208 Pb as coolant
Nuclear Engineering and Technology
2021 .02
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