지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
이용수
등록된 정보가 없습니다.
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
TOP-MOUNTED IN-CORE INSTRUMENTATION : CURRENT STATUS AND TECHNICAL ISSUES
에너지공학
2015 .06
Technology Selection for Offshore Underwater Small Modular Reactors
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
Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation
Nuclear Engineering and Technology
2018 .01
On the cyclic change in the dynamics of the IBR-2M pulsed reactor
Nuclear Engineering and Technology
2023 .05
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
Nuclear Engineering and Technology
2020 .01
A simple method for estimating the major nuclide fractional ?ssion rates within light water and advanced gas cooled reactors
Nuclear Engineering and Technology
2020 .09
Enhancing Utilization and Ensuring Security: Insights to Compromise Contradicting Conditions in New Research Reactors
Nuclear Engineering and Technology
2021 .05
신규 개발 저출력 연구용 원자로 구조물 집합체의 동특성 해석
대한기계학회 춘추학술대회
2018 .12
Comparative study on response of thiocyanate shock load on continuous and fed batch anaerobic-anoxic-aerobic sequential moving bed reactors
Environmental Engineering Research
2015 .03
Ex-vessel Steam Explosion Analysis for Pressurized Water Reactor and Boiling Water Reactor
Nuclear Engineering and Technology
2016 .01
Design of a direct-cycle supercritical CO2 nuclear reactor with heavy water moderation
Nuclear Engineering and Technology
2022 .03
Risk-informed design optimization method and application in a lead-based research reactor
Nuclear Engineering and Technology
2023 .06
Risk-informed approach to the safety improvement of the reactor protection system of the AGN-201K research reactor
Nuclear Engineering and Technology
2020 .01
AM600: A New Look at the Nuclear Steam Cycle
Nuclear Engineering and Technology
2017 .01
Conceptual Designs and Characteristic of the Fuel Handling and Transfer System for 150 MWe PGSFR and 1400 MWe SFR Burner Reactor
Nuclear Engineering and Technology
2022 .11
Inverse method to obtain reactivity in nuclear reactors with P1 point reactor kinetics model using matrix formulation
Nuclear Engineering and Technology
2021 .02
연구용 원자로 격자판에서의 온도분포 평가
대한기계학회 춘추학술대회
2017 .11
Self-pressurization analysis of the natural circulation integral nuclear reactor using a new dynamic model
Nuclear Engineering and Technology
2018 .01
Additive Manufacturing Based Design of Metal Continuous Flow Reactor of Inner Micro Structure for Continuous Mixing and Reaction of Chemical Solvents
Journal of the Korean Society for Precision Engineering
2021 .09
0