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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
LFR 태양열발전과 PV 발전시스템의 경제성 비교분석 연구
신·재생에너지
2016 .12
Code development on steady-state thermal-hydraulic for small modular natural circulation lead-based fast reactor
Nuclear Engineering and Technology
2020 .12
Code development and preliminary validation for lead-cooled fast reactor thermal-hydraulic transient behavior
Nuclear Engineering and Technology
2024 .06
Development and verification of a Monte Carlo two-step method for lead-based fast reactor neutronics analysis
Nuclear Engineering and Technology
2023 .06
FAST (Floating Absorber for Safety at Transient) for the Improved Safety of Sodium-cooled Burner Fast Reactors
Nuclear Engineering and Technology
2021 .06
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
Nuclear Engineering and Technology
2020 .01
Comparative analysis of internal flow characteristics of LBE-cooled fast reactor main coolant pump with different structures under reverse rotation accident conditions
Nuclear Engineering and Technology
2021 .07
Technology Selection for Offshore Underwater Small Modular Reactors
Nuclear Engineering and Technology
2016 .01
선형 프레넬 반사판 태양열 발전시스템의 설계 및 제작
융ㆍ복합기술연구소 논문집
2018 .01
Achieving wetting in molten lead for ultrasonic applications
Nuclear Engineering and Technology
2024 .02
Transient Diagnosis and Prognosis for Secondary System in Nuclear Power Plants
Nuclear Engineering and Technology
2016 .01
Assessment of N-16 activity concentration in Bangladesh Atomic Energy Commission TRIGA Research Reactor
Nuclear Engineering and Technology
2018 .01
Risk-informed design optimization method and application in a lead-based research reactor
Nuclear Engineering and Technology
2023 .06
LFR 태양열발전과 PV 발전시스템의 경제성 비교분석 연구
한국신·재생에너지학회 학술대회 초록집
2016 .05
Level 1 probabilistic safety assessment of supercritical ? CO 2 ? cooled micro modular reactor in conceptual design phase
Nuclear Engineering and Technology
2021 .02
Risk-informed approach to the safety improvement of the reactor protection system of the AGN-201K research reactor
Nuclear Engineering and Technology
2020 .01
Analysis of the thermal-mechanical behavior of SFR fuel pins during fast unprotected transient overpower accidents using the GERMINAL fuel performance code
Nuclear Engineering and Technology
2024 .03
Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation
Nuclear Engineering and Technology
2018 .01
TOP-MOUNTED IN-CORE INSTRUMENTATION : CURRENT STATUS AND TECHNICAL ISSUES
에너지공학
2015 .06
Transient Analysis of a Subcritical Reactor Core with a MOX-Fuel using the Birth-and-Death Model
Nuclear Engineering and Technology
2021 .06
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