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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
FAST (Floating Absorber for Safety at Transient) for the Improved Safety of Sodium-cooled Burner Fast Reactors
Nuclear Engineering and Technology
2021 .06
Development and validation of fuel stub motion model for the disrupted core of a sodium-cooled fast reactor
Nuclear Engineering and Technology
2021 .12
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
PWR core calculation based on pin-cell homogenization in three-dimensional pin-by-pin geometry
Nuclear Engineering and Technology
2024 .06
Evaluation of the reutilization of used nuclear fuel in a PWR core without reprocessing
Nuclear Engineering and Technology
2019 .01
아이핀 대량 부정발급 사고에 대한 개선방법 연구
디지털산업정보학회논문지
2015 .01
SIMMER-IV application to safety assessment of severe accident in a small SFR
Nuclear Engineering and Technology
2024 .03
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment
Nuclear Engineering and Technology
2021 .10
Development and verifi cation of pin-by-pin homogenized simplifi ed transport solver Tortin for PWR core analysis
Nuclear Engineering and Technology
2020 .11
Fracture simulation of SFR metallic fuel pin using fi nite element damage analysis method
Nuclear Engineering and Technology
2021 .03
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
High performance 3D pin-by-pin neutron diffusion calculation based on 2D/1D decoupling method for accurate pin power estimation
Nuclear Engineering and Technology
2021 .11
Solution of OECD/NEA PWR MOX/UO2 benchmark with a high-performance pin-by-pin core calculation code
Nuclear Engineering and Technology
2024 .09
Immune metabolism regulation of the germinal center response
Experimental and Molecular Medicine
2020 .01
Electro-Deposition of Cr Layer to Prevent Fuel Cladding Chemical Interaction in Sodium Fast Reactor (SFR)
한국방사성폐기물학회 학술대회
2017 .01
Simulation of reactivity-initiated accident transients on UO2 -M5® fuel rods with ALCYONE V1.5 fuel performance code
Nuclear Engineering and Technology
2018 .01
A pin to Multi-pin Calibration 시 설비 검증 방법
한국정밀공학회 학술발표대회 논문집
2015 .05
Transient Safety Analysis of M2LFR-1000 Reactor using ATHLET
Nuclear Engineering and Technology
2019 .01
Metal Fuel Development and Verifi cation for Prototype Generation IV Sodium-Cooled Fast Reactor
Nuclear Engineering and Technology
2016 .01
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