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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
Nuclear Engineering and Technology
2020 .01
연구용 원자로 격자판에서의 온도분포 평가
대한기계학회 춘추학술대회
2017 .11
Neutronics Analysis of a 200 kWe Space Nuclear Reactor with an Integrated Honeycomb Core Design
Nuclear Engineering and Technology
2022 .12
Assessment of N-16 activity concentration in Bangladesh Atomic Energy Commission TRIGA Research Reactor
Nuclear Engineering and Technology
2018 .01
연구용 원자로의 원자로 구조물 집합체 스트레이너에서의 압력강하 평가
대한기계학회 춘추학술대회
2018 .12
TOP-MOUNTED IN-CORE INSTRUMENTATION : CURRENT STATUS AND TECHNICAL ISSUES
에너지공학
2015 .06
High fidelity core flow measurement experiment for an advanced research reactor using a real scale mockup
Nuclear Engineering and Technology
2024 .09
개방수조형 연구용 원자로의 열출력 불확실도 평가
대한기계학회 춘추학술대회
2017 .11
Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation
Nuclear Engineering and Technology
2018 .01
신규 개발 저출력 연구용 원자로 구조물 집합체의 동특성 해석
대한기계학회 춘추학술대회
2018 .12
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
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
Thermal Hydraulic Analysis of Core Flow Bypass in a Typical Research Reactor
Nuclear Engineering and Technology
2019 .01
Study on an open fuel cycle of IVG.1M research reactor operating with LEU-fuel
Nuclear Engineering and Technology
2023 .04
Technology Selection for Offshore Underwater Small Modular Reactors
Nuclear Engineering and Technology
2016 .01
Design of a Mixed-Spectrum Reactor With Improved Proliferation Resistance for Long-Lived Applications
방사성폐기물학회지
2018 .01
Design of a direct-cycle supercritical CO2 nuclear reactor with heavy water moderation
Nuclear Engineering and Technology
2022 .03
Analysis of the flow distribution and mixing characteristics in the reactor pressure vessel
Nuclear Engineering and Technology
2021 .01
Risk-informed design optimization method and application in a lead-based research reactor
Nuclear Engineering and Technology
2023 .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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