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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
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
무제어봉 원자로의 고유안전 개념을 지니는 Density Lock 내부 열성층화 불안정성에 대한 고찰
한국유체기계학회 논문집
2023 .12
Neutronics Analysis of a 200 kWe Space Nuclear Reactor with an Integrated Honeycomb Core Design
Nuclear Engineering and Technology
2022 .12
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
Nuclear Engineering and Technology
2020 .01
Transient Analysis of a Subcritical Reactor Core with a MOX-Fuel using the Birth-and-Death Model
Nuclear Engineering and Technology
2021 .06
Analysis of APR1400 Restarting Using Fixed Boron Dilution Rate Approach
에너지공학
2021 .03
Design of a direct-cycle supercritical CO2 nuclear reactor with heavy water moderation
Nuclear Engineering and Technology
2022 .03
TOP-MOUNTED IN-CORE INSTRUMENTATION : CURRENT STATUS AND TECHNICAL ISSUES
에너지공학
2015 .06
Feasibility study of a dedicated nuclear desalination system: Low-pressure Inherent heat sink Nuclear Desalination plant (LIND)
Nuclear Engineering and Technology
2015 .04
Inverse method to obtain reactivity in nuclear reactors with P1 point reactor kinetics model using matrix formulation
Nuclear Engineering and Technology
2021 .02
Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation
Nuclear Engineering and Technology
2018 .01
Burnable Absorber Design Study for a Passively-Cooled Molten Salt Fast Reactor
Nuclear Engineering and Technology
2024 .03
Assessment of N-16 activity concentration in Bangladesh Atomic Energy Commission TRIGA Research Reactor
Nuclear Engineering and Technology
2018 .01
Analysis of the CREOLE experiment on the reactivity temperature coefficient of the UO2 light water moderated lattices using Monte Carlo transport calculations and ENDF/B-VII.1 nuclear data library
Nuclear Engineering and Technology
2020 .01
개방수조형 연구용 원자로의 열출력 불확실도 평가
대한기계학회 춘추학술대회
2017 .11
FAST (Floating Absorber for Safety at Transient) for the Improved Safety of Sodium-cooled Burner Fast Reactors
Nuclear Engineering and Technology
2021 .06
Application of TULIP/STREAM code in 2-D fast reactor core high-fidelity neutronic analysis
Nuclear Engineering and Technology
2019 .01
Ultrasonic ranging technique for obstacle monitoring above reactor core in prototype generation IV sodium-cooled fast reactor
Nuclear Engineering and Technology
2020 .01
Adaptive energy group division in the few-group cross-section generation for full spectrum reactor modeling with deterministic method
Nuclear Engineering and Technology
2024 .06
Design of a Mixed-Spectrum Reactor With Improved Proliferation Resistance for Long-Lived Applications
방사성폐기물학회지
2018 .01
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