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Development of dynamic motion models of SPACE code for ocean nuclear reactor analysis
Nuclear Engineering and Technology
2022 .03
Multi-Scale and Multi-Physics Approach to Safety Analysis of Nuclear Reactor
한국전산유체공학회 학술대회논문집
2022 .10
Simulation-based Anomaly Detection in Nuclear Reactors
대한산업공학회 추계학술대회 논문집
2020 .11
Technology Selection for Offshore Underwater Small Modular Reactors
Nuclear Engineering and Technology
2016 .01
시뮬레이션 데이터 생성을 통한 기계학습 기반 원자로 노심 이상 탐지 방법론
대한산업공학회지
2021 .04
Inverse method to obtain reactivity in nuclear reactors with P1 point reactor kinetics model using matrix formulation
Nuclear Engineering and Technology
2021 .02
Risk-informed design optimization method and application in a lead-based research reactor
Nuclear Engineering and Technology
2023 .06
Enhancing Utilization and Ensuring Security: Insights to Compromise Contradicting Conditions in New Research Reactors
Nuclear Engineering and Technology
2021 .05
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
OCEANS 2018
대한조선학회지
2018 .12
TOP-MOUNTED IN-CORE INSTRUMENTATION : CURRENT STATUS AND TECHNICAL ISSUES
에너지공학
2015 .06
Design of an Organic Simplified Nuclear Reactor
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
Development of classification criteria for non-reactor nuclear facilities in Korea
Nuclear Engineering and Technology
2023 .02
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
Risk-informed approach to the safety improvement of the reactor protection system of the AGN-201K research reactor
Nuclear Engineering and Technology
2020 .01
A new design concept for ocean nuclear power plants using tension leg platform
Structural Engineering and Mechanics, An Int'l Journal
2020 .01
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
Nuclear Engineering and Technology
2020 .01
Study on Nuclear Test Scheme and Test Results for Safety Neutron Measurement System in Research Reactor
한국방사성폐기물학회 학술대회
2017 .01
Moving reactor model for the MULTID components of the system thermal-hydraulic analysis code MARS-KS
Nuclear Engineering and Technology
2022 .11
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