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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code
Nuclear Engineering and Technology
2020 .12
Investigation of Pellet-Clad Mechanical Interaction in Failed Spent PWR Fuel
Corrosion Science and Technology
2019 .01
High-fidelity numerical investigation on structural integrity of SFR fuel cladding during design basis events
Nuclear Engineering and Technology
2024 .02
Systems Engineering Approach to the Heat Transfer Analysis of PLUS 7 Fuel Rod Using ANSYS FEM Code
시스템엔지니어링학술지
2017 .01
Validation of the fuel rod performance analysis code FRIPAC
Nuclear Engineering and Technology
2019 .01
Effect of central hole on fuel temperature distribution
Nuclear Engineering and Technology
2017 .01
Vibration Control of a Nuclear Fuel Rod Maneuvering Under Water
제어로봇시스템학회 국제학술대회 논문집
2015 .10
Modeling of central void formation in LWR fuel pellets due to high-temperature restructuring
Nuclear Engineering and Technology
2018 .01
Monitoring of Fuel and Cladding Elongation in a Nuclear Fuel Rod
Journal of the Korean Society for Precision Engineering
2017 .07
FALCON code-based analysis of PWR fuel rod behaviour during RIA transients versus new U.S.NRC and current Swiss failure limits
Nuclear Engineering and Technology
2021 .11
Heat Transfer Analysis of PLUS7 Fuel Rod For APR1400 Using ANSYS
대한기계학회 춘추학술대회
2016 .12
Experimental evaluation of fuel rod pattern analysis in fuel assembly using Yonsei single-photon emission computed tomography (YSECT)
Nuclear Engineering and Technology
2022 .06
Criticality Safety Study for Loss of Single Fuel Rod From WH 14 Type Fuel
한국방사성폐기물학회 학술대회
2018 .01
A comparative study on the impact of Gd2O3 burnable neutron absorber in UO2 and (U, Th)O2 fuels
Nuclear Engineering and Technology
2020 .01
Design and evaluation of an innovative LWR fuel combined dual-cooled annular geometry and SiC cladding materials
Nuclear Engineering and Technology
2021 .01
Parametric study on the structural response of a high burnup spent nuclear fuel rod under drop impact considering post-irradiated fuel conditions
Nuclear Engineering and Technology
2020 .01
연료품질 및 연비계산 방법 변화에 따른 연비특성 분석
동력시스템공학회지
2016 .08
Development of mechanistic cladding rupture model for severe accident analysis and application in PHEBUS FPT3 experiment
Nuclear Engineering and Technology
2022 .01
Investigation on the effect of eccentricity for fuel disc irradiation tests
Nuclear Engineering and Technology
2021 .05
정상운반조건 해석을 위한 사용후핵연료집합체 유한요소모델 최적화
한국압력기기공학회 논문집
2023 .12
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