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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
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
Theoretical models of threshold stress intensity factor and critical hydride length for delayed hydride cracking considering thermal stresses
Nuclear Engineering and Technology
2018 .01
Methodology of Delayed Hydride Cracking Assessment of Spent Fuel Cladding
한국방사성폐기물학회 학술대회
2017 .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
Micro-cantilever Tests on Hydride Blister and Zirconium Matrix of Zircaloy-4 Cladding Tube
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
비조사 Zircaloy-4 피복관의 링압축 고온 특성 평가
대한기계학회 춘추학술대회
2024 .11
On the effect of temperature on the threshold stress intensity factor of delayed hydride cracking in light water reactor fuel cladding
Nuclear Engineering and Technology
2017 .06
Three-dimensional Numerical Simulation of Hydrogen-induced Multi-field Coupling Behavior in Cracked Zircaloy Cladding Tubes
Nuclear Engineering and Technology
2019 .01
Influence of hydrogen concentration on burst parameters of Zircaloy-4 cladding tube under simulated loss-of-coolant accident
Nuclear Engineering and Technology
2020 .09
Understanding the role of hydrogen on creep behaviour of Zircaloy-4 cladding tubes using nanoindentation
Nuclear Engineering and Technology
2020 .09
소형 수소저장물질 유효열전도도 측정장치의 신뢰성 평가
한국수소및신에너지학회논문집
2015 .10
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 initial coating crack on the mechanical performance of surface-coated zircaloy cladding
Nuclear Engineering and Technology
2021 .04
Improvement of delayed hydride cracking assessment of PWR spent fuel during dry storage
Nuclear Engineering and Technology
2020 .01
Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage
Nuclear Engineering and Technology
2017 .01
Fatigue Life Characterization of Simulated Fuel Cladding to Hydride Contents for Normal Transportation Integrity
한국방사성폐기물학회 학술대회
2019 .01
The effect of neutron irradiation on hydride reorientation and mechanical property degradation of zirconium alloy cladding
Nuclear Engineering and Technology
2017 .01
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