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PASTELS project - overall progress of the project on experimental and numerical activities on passive safety systems
Nuclear Engineering and Technology
2024 .03
Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiments using TRACE
Nuclear Engineering and Technology
2018 .01
Assessment of CATHARE code against DEC-A upper head SBLOCA experiments
Nuclear Engineering and Technology
2024 .03
A Comparative Study on Mitigation Alternatives in Response to an Extended SBO for APR1400 Using Systems Engineering
시스템엔지니어링학술지
2016 .01
ROSA/LSTF Test and RELAP5 Analyses on PWR Cold Leg Small-Break LOCA with Accident Management Measure and PKL Counterpart Test
Nuclear Engineering and Technology
2017 .01
The concept of the innovative power reactor
Nuclear Engineering and Technology
2017 .01
Simulation and transient analyses of a complete passive heat removal system in a downward cooling pool-type material testing reactor against a complete station blackout and long-term natural convection mode using the RELAP5/3.2 code
Nuclear Engineering and Technology
2017 .01
Uncertainty analysis of ROSA/LSTF test by RELAP5 code and PKL counterpart test concerning PWR hot leg break LOCAs
Nuclear Engineering and Technology
2018 .01
EVALUATION OF AN ACCIDENT MANAGEMENT STRATEGY OF EMERGENCY WATER INJECTION USING FIRE ENGINES IN A TYPICAL PRESSURIZED WATER REACTOR
Nuclear Engineering and Technology
2015 .01
피동안전주입계통 열수력현상에 대한 실험적 연구
대한기계학회 춘추학술대회
2016 .12
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
Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea
Nuclear Engineering and Technology
2016 .01
Performance analysis of the passive safety features of iPOWER under Fukushima-like accident conditions
Nuclear Engineering and Technology
2019 .01
Numerical investigation of two-phase natural convection and temperature stratifi cation phenomena in a rectangular enclosure with conjugate heat transfer
Nuclear Engineering and Technology
2020 .01
Thermal-hydraulic study of air-cooled passive decay heat removal system for APR+ under extended station blackout
Nuclear Engineering and Technology
2019 .01
Application of Chernoff bound to passive system reliability evaluation for probabilistic safety assessment of nuclear power plants
Nuclear Engineering and Technology
2022 .08
Assessment of the core-catcher in the VVER-1000 reactor containment under various severe accidents
Nuclear Engineering and Technology
2023 .01
고속 회전축 방열용 루프형 2상유동 열사이폰 열교환기의 응축열전달 성능에 관한 연구
대한기계학회 춘추학술대회
2015 .11
SAFETY ANALYSIS OF INCREASE IN HEAT REMOVAL FROM REACTOR COOLANT SYSTEM WITH INADVERTENT OPERATION OF PASSIVE RESIDUAL HEAT REMOVAL AT NO-LOAD CONDITIONS
Nuclear Engineering and Technology
2015 .01
학교생활안전사고예방을 위한 학교시설 안전점검 개선 방향에 관한 연구
대한건축학회 학술발표대회 논문집
2021 .04
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