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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Effects of Hydride Re-orientation and Hydride Rim on Fracture Energy of Zircaloy-4 Cladding
한국방사성폐기물학회 학술대회
2018 .01
Hydrogen Content Effects on Delayed Hydride Cracking in Zircaloy-4 Cladding
한국방사성폐기물학회 학술대회
2018 .01
Effects of Zr-hydride distribution of irradiated Zircaloy-3 cladding in RIA-simulating pellet-clad mechanical interaction testing
Nuclear Engineering and Technology
2018 .01
소형 수소저장물질 유효열전도도 측정장치의 신뢰성 평가
한국수소및신에너지학회논문집
2015 .10
Effect of Inhomogeneous Nucleation of Hydride at α/β Phase Boundary on Microstructure Evolution of Zr–2.5 wt%Nb Pressure Tube
Metals and Materials International
2019 .01
The effect of neutron irradiation on hydride reorientation and mechanical property degradation of zirconium alloy cladding
Nuclear Engineering and Technology
2017 .01
Micro-cantilever Tests on Hydride Blister and Zirconium Matrix of Zircaloy-4 Cladding Tube
한국방사성폐기물학회 학술대회
2019 .01
Measurement of Threshold Stress Intensity Factor of Delayed Hydride Cracking for Unirradiated Zircaloy-4 Cladding
한국방사성폐기물학회 학술대회
2019 .01
Effect of Long-term Cooling on the Hydride Reorientation of Non-irradiated Zircaloy-4 Cladding Tube : 1M, 3M & 6M
한국방사성폐기물학회 학술대회
2019 .01
Methodology of Delayed Hydride Cracking Assessment of Spent Fuel Cladding
한국방사성폐기물학회 학술대회
2017 .01
Theoretical models of threshold stress intensity factor and critical hydride length for delayed hydride cracking considering thermal stresses
Nuclear Engineering and Technology
2018 .01
Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage
Nuclear Engineering and Technology
2017 .01
Predicting Amount of Radial Hydrides in Spent Fuel During Dry Storage
한국방사성폐기물학회 학술대회
2018 .01
A New Perspective of Hydride Re-orientation in SNF
한국방사성폐기물학회 학술대회
2017 .01
Fatigue Life Characterization of Simulated Fuel Cladding to Hydride Contents for Normal Transportation Integrity
한국방사성폐기물학회 학술대회
2019 .01
Three-dimensional Numerical Simulation of Hydrogen-induced Multi-field Coupling Behavior in Cracked Zircaloy Cladding Tubes
Nuclear Engineering and Technology
2019 .01
Fundamental Study on Actuation System Development using Temperature Control of Metal-Hydride Module for a Rehabilitative System
한국정밀공학회 학술발표대회 논문집
2019 .05
Methodology for numerical evaluation of fracture resistance under pinch loading of spent nuclear fuel cladding containing reoriented hydrides
Nuclear Engineering and Technology
2024 .06
재활시스템 구동원 적용을 위한 수소저장합금 모듈 설계
한국정밀공학회 학술발표대회 논문집
2015 .12
Cooldown-Induced Hydride Reorientation of Hydrogen-Charged Zirconium Alloy Cladding Tubes
Metals and Materials International
2015 .01
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