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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
개방수조형 연구용 원자로의 열출력 불확실도 평가
대한기계학회 춘추학술대회
2017 .11
Discharge header design inside a reactor pool for flow stability in a research reactor
Nuclear Engineering and Technology
2020 .10
Design of the flexible switching controller for small PWR core power control with the multi-model
Nuclear Engineering and Technology
2021 .03
이종 냉각수 활용 3중 열교환기 적용 전동식 냉방시스템 성능 특성 연구
한국자동차공학회 춘계학술대회
2016 .05
System-Level Simulation of Active Cooling Control in an Automotive Engine through the Application of Electronically-map-controlled Thermostat
한국자동차공학회논문집
2017 .07
연구용 원자로의 원자로 구조물 집합체 스트레이너에서의 압력강하 평가
대한기계학회 춘추학술대회
2018 .12
마이크로채널 반응기를 이용한 강화된 저온 피셔-트롭쉬 합성반응의 전산유체역학적 해석
한국가스학회지
2017 .08
Analysis of the flow distribution and mixing characteristics in the reactor pressure vessel
Nuclear Engineering and Technology
2021 .01
Study on bidirectional fluid-solid coupling characteristics of reactor coolant pump under steady-state condition
Nuclear Engineering and Technology
2019 .01
State-Space Model Predictive Control Method for Core Power Control in Pressurized Water Reactor Nuclear Power Stations
Nuclear Engineering and Technology
2017 .01
티타늄 가공 시 절삭 온도에 따른 절삭유 공급 조절 전략 연구
한국생산제조학회 학술발표대회 논문집
2020 .12
Design of Honing Coolant Temperature Control System Based on Fuzzy Self-tuning PID
한국정보전자통신기술학회 논문지
2018 .04
Transient full core analysis of PWR with multi-scale and multi-physics approach
Nuclear Engineering and Technology
2024 .03
Supercritical CO2-cooled fast reactor and cold shutdown system for ship propulsion
Nuclear Engineering and Technology
2024 .03
Robust power control design for a small pressurized water reactor using an H infinity mixed sensitivity method
Nuclear Engineering and Technology
2020 .01
Development and verification of PWR core transient coupling calculation software
Nuclear Engineering and Technology
2021 .11
Uncertainty quantifi cation in decay heat calculation of spent nuclear fuel by STREAM/RAST-K
Nuclear Engineering and Technology
2021 .09
Numerical Study on Coolant Flow Distribution at the Core Inlet for an Integral Pressurized Water Reactor
Nuclear Engineering and Technology
2017 .01
Study on load tracking characteristics of closed Brayton conversion liquid metal cooled space nuclear power system
Nuclear Engineering and Technology
2024 .05
냉각재 과온도 온도편차 설정치의 허용값 평가방법 제안
한국에너지학회 학술발표회
2017 .09
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