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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Aspects of Preliminary Probabilistic Safety Assessment for a Research Reactor in the Conceptual Design Phase
한국안전학회지
2019 .01
PSA를 이용한 연구용 원자로 안전성 향상 방안 도출
한국안전학회지
2018 .01
Risk-informed design optimization method and application in a lead-based research reactor
Nuclear Engineering and Technology
2023 .06
원자력발전소의 화재사건 확률론적안전성평가 모델 구축에 관한 연구
한국안전학회지
2016 .01
Risk-informed approach to the safety improvement of the reactor protection system of the AGN-201K research reactor
Nuclear Engineering and Technology
2020 .01
Technology Selection for Offshore Underwater Small Modular Reactors
Nuclear Engineering and Technology
2016 .01
시스템엔지니어링 방법을 적용한 노심용융방지 초소형 모듈원자로 국내 개발타당성 검토
시스템엔지니어링학술지
2019 .01
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
Nuclear Engineering and Technology
2020 .01
Advanced Reactor Passive System Reliability Demonstration Analysis for an External Event
Nuclear Engineering and Technology
2017 .01
Evaluating direct vessel injection accident-event progression of AP1000 and key figures of merit to support the design and development of water-cooled small modular reactors
Nuclear Engineering and Technology
2024 .06
냉각재상실사고 시 안전주입탱크 유로저항계수가 일체형 원자로에 미치는 영향
대한기계학회 춘추학술대회
2020 .12
Assessment of N-16 activity concentration in Bangladesh Atomic Energy Commission TRIGA Research Reactor
Nuclear Engineering and Technology
2018 .01
An integrated risk-informed safety classification for unique research reactors
Nuclear Engineering and Technology
2023 .05
TOP-MOUNTED IN-CORE INSTRUMENTATION : CURRENT STATUS AND TECHNICAL ISSUES
에너지공학
2015 .06
Design of a direct-cycle supercritical CO2 nuclear reactor with heavy water moderation
Nuclear Engineering and Technology
2022 .03
Enhancing Utilization and Ensuring Security: Insights to Compromise Contradicting Conditions in New Research Reactors
Nuclear Engineering and Technology
2021 .05
INSTRUMENTATION AND CONTROL STRATEGIES FOR AN INTEGRAL PRESSURIZED WATER REACTOR
Nuclear Engineering and Technology
2015 .01
Safety Classification of Systems, Structures and Components for Pool Type Research Reactor
Nuclear Engineering and Technology
2016 .01
Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea
Nuclear Engineering and Technology
2016 .01
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