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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
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
Effect of central hole on fuel temperature distribution
Nuclear Engineering and Technology
2017 .01
SiC 복합체 보호막 금속 피복관의 개발 및 고온산화 특성 분석
한국표면공학회지
2015 .10
Development of FEMAXI-ATF for analyzing PCMI behavior of SiC cladded fuel under power ramp conditions
Nuclear Engineering and Technology
2024 .03
Monitoring of Fuel and Cladding Elongation in a Nuclear Fuel Rod
Journal of the Korean Society for Precision Engineering
2017 .07
Preliminary Study of Annular Fuel Fabrication Using Hot Extrusion Method
한국방사성폐기물학회 학술대회
2019 .01
Development of Fabrication Technology of Annular Fuel by Hot Extrusion Method
한국방사성폐기물학회 학술대회
2018 .01
Systems Engineering Approach to the Heat Transfer Analysis of PLUS 7 Fuel Rod Using ANSYS FEM Code
시스템엔지니어링학술지
2017 .01
Heat Transfer Analysis of PLUS7 Fuel Rod For APR1400 Using ANSYS
대한기계학회 춘추학술대회
2016 .12
High-fidelity numerical investigation on structural integrity of SFR fuel cladding during design basis events
Nuclear Engineering and Technology
2024 .02
Cool SiC™ (SiC Mosfet)의 특징과 응용
전력전자학회지
2019 .04
Development Status of Accident-tolerant Fuel for Light Water Reactors in Korea
Nuclear Engineering and Technology
2016 .01
디젤엔진에서 에멀젼 연료와 천연가스 이중연료의 배기가스 배출 특성
동력시스템공학회지
2021 .10
Effect of Hydrogen on Mechanical Behavior of Zr-based Alloy Fuel Cladding at High Temperature
한국방사성폐기물학회 학술대회
2018 .01
Investigation of Pellet-Clad Mechanical Interaction in Failed Spent PWR Fuel
Corrosion Science and Technology
2019 .01
이중냉각 환형핵연료 집합체를 위한 비틀림 혼합날개 지지격자의 강제대류열전달 성능 검토
대한기계학회 논문집 B권
2017 .01
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment
Nuclear Engineering and Technology
2021 .10
Development of Spent Fuel Cladding Degradation Model in Integrated Platform
한국방사성폐기물학회 학술대회
2018 .01
Metal Fuel Development and Verifi cation for Prototype Generation IV Sodium-Cooled Fast Reactor
Nuclear Engineering and Technology
2016 .01
Numerical simulation of the effects of localized cladding oxidation on LWR fuel rod design limits using a SLICE-DO model of the FALCON code
Nuclear Engineering and Technology
2020 .01
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