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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Methodology of Delayed Hydride Cracking Assessment of Spent Fuel Cladding
한국방사성폐기물학회 학술대회
2017 .01
Effects of Hydride Re-orientation and Hydride Rim on Fracture Energy of Zircaloy-4 Cladding
한국방사성폐기물학회 학술대회
2018 .01
Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage
Nuclear Engineering and Technology
2017 .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
Temperature-dependent axial mechanical properties of Zircaloy-4 with various hydrogen amounts and hydride orientations
Nuclear Engineering and Technology
2022 .05
Hydrogen Content Effects on Delayed Hydride Cracking in Zircaloy-4 Cladding
한국방사성폐기물학회 학술대회
2018 .01
Methodology for numerical evaluation of fracture resistance under pinch loading of spent nuclear fuel cladding containing reoriented hydrides
Nuclear Engineering and Technology
2024 .06
Measures for the Failure Evaluation of SNF Cladding During the Transportation
한국방사성폐기물학회 학술대회
2018 .01
소형 수소저장물질 유효열전도도 측정장치의 신뢰성 평가
한국수소및신에너지학회논문집
2015 .10
Data analysis of simulated fuel-loaded sea transportation tests under normal conditions of transport
Nuclear Engineering and Technology
2024 .02
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
Effect of Creep Deformation on Ductility of Simulated Spent Fuel Cladding
한국방사성폐기물학회 학술대회
2018 .01
High-fidelity numerical investigation on structural integrity of SFR fuel cladding during design basis events
Nuclear Engineering and Technology
2024 .02
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
Predicting Amount of Radial Hydrides in Spent Fuel During Dry Storage
한국방사성폐기물학회 학술대회
2018 .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
Laser cladding 표면의 젖음성 평가
한국트라이볼로지학회 학술대회
2019 .04
Improvement of delayed hydride cracking assessment of PWR spent fuel during dry storage
Nuclear Engineering and Technology
2020 .01
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