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!
INSTRUMENTATION AND CONTROL STRATEGIES FOR AN INTEGRAL PRESSURIZED WATER REACTOR
Nuclear Engineering and Technology
2015 .01
Ex-vessel Steam Explosion Analysis for Pressurized Water Reactor and Boiling Water Reactor
Nuclear Engineering and Technology
2016 .01
TOP-MOUNTED IN-CORE INSTRUMENTATION : CURRENT STATUS AND TECHNICAL ISSUES
에너지공학
2015 .06
AM600: A New Look at the Nuclear Steam Cycle
Nuclear Engineering and Technology
2017 .01
Technology Selection for Offshore Underwater Small Modular Reactors
Nuclear Engineering and Technology
2016 .01
Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation
Nuclear Engineering and Technology
2018 .01
Inverse method to obtain reactivity in nuclear reactors with P1 point reactor kinetics model using matrix formulation
Nuclear Engineering and Technology
2021 .02
Assessment of N-16 activity concentration in Bangladesh Atomic Energy Commission TRIGA Research Reactor
Nuclear Engineering and Technology
2018 .01
연구용 원자로 수조 내에서의 자연대류 해석
한국전산유체공학회 학술대회논문집
2015 .05
Enhancing Utilization and Ensuring Security: Insights to Compromise Contradicting Conditions in New Research Reactors
Nuclear Engineering and Technology
2021 .05
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
Nuclear Engineering and Technology
2020 .01
연구용 원자로의 원자로 구조물 집합체 스트레이너에서의 압력강하 평가
대한기계학회 춘추학술대회
2018 .12
Design of an Organic Simplified Nuclear Reactor
Nuclear Engineering and Technology
2016 .01
Steam generator performance improvements for integral small modular reactors
Nuclear Engineering and Technology
2017 .01
연구용 원자로에서 자연대류 냉각 시 원자로구조물 유동의 전산유체역학 분석
대한기계학회 춘추학술대회
2019 .11
On the cyclic change in the dynamics of the IBR-2M pulsed reactor
Nuclear Engineering and Technology
2023 .05
Numerical study on thermal-hydraulics of external reactor vessel cooling in high-power reactor using MARS-KS1.5 code: CFD-aided estimation of natural circulation flow rate
Nuclear Engineering and Technology
2022 .01
Design of digital nuclear power small reactor once-through steam generator control system
Nuclear Engineering and Technology
2022 .07
Risk-informed design optimization method and application in a lead-based research reactor
Nuclear Engineering and Technology
2023 .06
Electric power frequency and nuclear safety - Subsynchronous Resonance case study
Nuclear Engineering and Technology
2019 .01
0