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Hydrogen Content Effects on Delayed Hydride Cracking in Zircaloy-4 Cladding
한국방사성폐기물학회 학술대회
2018 .01
Effects of Hydride Re-orientation and Hydride Rim on Fracture Energy of Zircaloy-4 Cladding
한국방사성폐기물학회 학술대회
2018 .01
Effect of Long-term Cooling on the Hydride Reorientation of Non-irradiated Zircaloy-4 Cladding Tube : 1M, 3M & 6M
한국방사성폐기물학회 학술대회
2019 .01
Temperature-dependent axial mechanical properties of Zircaloy-4 with various hydrogen amounts and hydride orientations
Nuclear Engineering and Technology
2022 .05
Measurement of Threshold Stress Intensity Factor of Delayed Hydride Cracking for Unirradiated Zircaloy-4 Cladding
한국방사성폐기물학회 학술대회
2019 .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
Review on the Control of the Direction of Hydride in Zirconium Clad Tube in Terms of Manufacturing Process
한국방사성폐기물학회 학술대회
2019 .01
비조사 Zircaloy-4 피복관의 링압축 고온 특성 평가
대한기계학회 춘추학술대회
2024 .11
Influence of hydrogen concentration on burst parameters of Zircaloy-4 cladding tube under simulated loss-of-coolant accident
Nuclear Engineering and Technology
2020 .09
Effect of Hoop Stress on the Hydride Reorientation of Non-irradiated Zircaloy-4 Cladding Tube : 90 MPa, 120 MPa & 150 MPa
한국방사성폐기물학회 학술대회
2018 .01
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 a surface oxide-dispersion-strengthened layer on mechanical strength of Zircaloy-5 tubes
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
Theoretical models of threshold stress intensity factor and critical hydride length for delayed hydride cracking considering thermal stresses
Nuclear Engineering and Technology
2018 .01
Three-dimensional Numerical Simulation of Hydrogen-induced Multi-field Coupling Behavior in Cracked Zircaloy Cladding Tubes
Nuclear Engineering and Technology
2019 .01
The effect of neutron irradiation on hydride reorientation and mechanical property degradation of zirconium alloy cladding
Nuclear Engineering and Technology
2017 .01
Methodology of Delayed Hydride Cracking Assessment of Spent Fuel Cladding
한국방사성폐기물학회 학술대회
2017 .01
Understanding the role of hydrogen on creep behaviour of Zircaloy-4 cladding tubes using nanoindentation
Nuclear Engineering and Technology
2020 .09
Effect of Thermal Cycling on the Hydride Reorientation of Non-irradiated Zircaloy-4 Cladding Tube : 1 Cy, 3 Cy & 10 Cy
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
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