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!
Multi-Scale and Multi-Physics Approach to Safety Analysis of Nuclear Reactor
한국전산유체공학회 학술대회논문집
2022 .10
CFD/RELAP5 Coupling Analysis of the ISP No. 43 Boron Dilution Experiment
Nuclear Engineering and Technology
2022 .01
Transient full core analysis of PWR with multi-scale and multi-physics approach
Nuclear Engineering and Technology
2024 .03
Study on bidirectional fluid-solid coupling characteristics of reactor coolant pump under steady-state condition
Nuclear Engineering and Technology
2019 .01
히트파이프 냉각 원자로 노심 다물리 해석을 위한 열-구조 코드 연계 시스템 수립
한국유체기계학회 학술대회 논문집
2021 .07
Physics-Based State of Charge and Energy Estimation Framework Using Physics-Informed Deep Learning Model
대한산업공학회 추계학술대회 논문집
2024 .10
Review of researches on coupled system and CFD codes
Nuclear Engineering and Technology
2021 .09
Design and construction of fluid-to-fluid scaled-down small modular reactor platform: As a testbed for the nuclear-based hydrogen production
Nuclear Engineering and Technology
2024 .03
개방수조형 연구용 원자로의 열출력 불확실도 평가
대한기계학회 춘추학술대회
2017 .11
연구용 원자로의 원자로 구조물 집합체 스트레이너에서의 압력강하 평가
대한기계학회 춘추학술대회
2018 .12
Design to Prevent Interference with Pool Platforms for a Research Reactor
한국에너지학회 학술발표회
2023 .10
Fluid-structure interaction problems solution by operator split methods and efficient software development by code-coupling
Coupled systems mechanics
2016 .01
Application of TULIP/STREAM code in 2-D fast reactor core high-fidelity neutronic analysis
Nuclear Engineering and Technology
2019 .01
Development of supporting platform for the fine flow characteristics of reactor core
Nuclear Engineering and Technology
2024 .05
다자유도 체험 이동 플랫폼 개발
한국정밀공학회 학술발표대회 논문집
2017 .05
Development and verification of PWR core transient coupling calculation software
Nuclear Engineering and Technology
2021 .11
열전달 결합 기법에 따른 열적 결빙보호장치 수치해석 개발
한국전산유체공학회지
2022 .12
Multi-physics processing and optimization of thick, and multi-directional carbon fiber prepregs
대한기계학회 춘추학술대회
2024 .06
신규 개발 저출력 연구용 원자로 구조물 집합체의 동특성 해석
대한기계학회 춘추학술대회
2018 .12
Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation
Nuclear Engineering and Technology
2018 .01
0