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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Development and testing of multicomponent fuel cladding with enhanced accidental performance
Nuclear Engineering and Technology
2020 .01
AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M6 cladding
Nuclear Engineering and Technology
2018 .01
Development of Innovative Light Water Reactor Nuclear Fuel Using 3D Printing Technology
Journal of the Korean Society for Precision Engineering
2016 .04
Electro-Deposition of Cr Layer to Prevent Fuel Cladding Chemical Interaction in Sodium Fast Reactor (SFR)
한국방사성폐기물학회 학술대회
2017 .01
Effect of initial coating crack on the mechanical performance of surface-coated zircaloy cladding
Nuclear Engineering and Technology
2021 .04
Effectiveness of Ni-based and Fe-based cladding alloys in delaying hydrogen generation for small modular reactors with increased accident tolerance
Nuclear Engineering and Technology
2023 .01
Microstructural characterization of accident tolerant fuel cladding with Cr?Al alloy coating layer after oxidation at 1200 °C in a steam environment
Nuclear Engineering and Technology
2020 .10
Mechanical analysis of surface-coated zircaloy cladding
Nuclear Engineering and Technology
2017 .01
Development Status of Accident-tolerant Fuel for Light Water Reactors in Korea
Nuclear Engineering and Technology
2016 .01
Characteristic of Zircaloy-fuel Mechanical Interaction in Failed Spent PWR Fuel
한국방사성폐기물학회 학술대회
2018 .01
Development of Cr coating to prevent FCCI (Fuel-Cladding Chemical Interaction)
한국표면공학회 학술발표회 초록집
2017 .11
Performance evaluation of Accident Tolerant Fuel under station blackout accident in PWR nuclear power plant by improved ISAA code
Nuclear Engineering and Technology
2022 .07
Effect of Hydrogen on Mechanical Behavior of Zr-based Alloy Fuel Cladding at High Temperature
한국방사성폐기물학회 학술대회
2018 .01
High-temperature oxidation behaviors of ZrSi2 and its coating on the surface of Zircaloy-4 tube by laser 3D printing
Nuclear Engineering and Technology
2020 .09
다중고장사고에 대한 크롬 코팅 피복관 사고저항성핵연료의 성능 분석 및 고찰
한국유체기계학회 학술대회 논문집
2023 .12
Monitoring of Fuel and Cladding Elongation in a Nuclear Fuel Rod
Journal of the Korean Society for Precision Engineering
2017 .07
Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding
Nuclear Engineering and Technology
2016 .01
Searching for the viability of using thorium-based accident-tolerant fuel for VVER-1200
Nuclear Engineering and Technology
2024 .01
Design and evaluation of an innovative LWR fuel combined dual-cooled annular geometry and SiC cladding materials
Nuclear Engineering and Technology
2021 .01
An evaluation on in-pile behaviors of SiC f /SiC cladding under normal and accident conditions with updated FROBA-ATF code
Nuclear Engineering and Technology
2021 .04
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