지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
이용수
등록된 정보가 없습니다.
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
Predicting Amount of Radial Hydrides in Spent Fuel During Dry Storage
한국방사성폐기물학회 학술대회
2018 .01
Development of Spent Fuel Cladding Degradation Model in Integrated Platform
한국방사성폐기물학회 학술대회
2018 .01
Improvement of delayed hydride cracking assessment of PWR spent fuel during dry storage
Nuclear Engineering and Technology
2020 .01
Effects of Hydride Re-orientation and Hydride Rim on Fracture Energy of Zircaloy-4 Cladding
한국방사성폐기물학회 학술대회
2018 .01
Peak Cladding Temperature Analysis of a Spent Fuel Assembly According to Heat Transfer Modes
한국방사성폐기물학회 학술대회
2018 .01
Fatigue Life Characterization of Simulated Fuel Cladding to Hydride Contents for Normal Transportation Integrity
한국방사성폐기물학회 학술대회
2019 .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
Measurement of Threshold Stress Intensity Factor of Delayed Hydride Cracking for Unirradiated Zircaloy-4 Cladding
한국방사성폐기물학회 학술대회
2019 .01
Effect of Creep Deformation on Ductility of Simulated Spent Fuel Cladding
한국방사성폐기물학회 학술대회
2018 .01
The Effective Thermal Conductivity of Spent Fuel Assemblies for Spent Fuel Storage
한국방사성폐기물학회 학술대회
2016 .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
Improvement of Spent Fuel Inspection System
한국방사성폐기물학회 학술대회
2017 .01
Development of Spent Fuel Nuclear Characteristic Evaluation System
한국방사성폐기물학회 학술대회
2019 .01
Confirmatory Procedure of Spent Fuel Information for Spent Fuel Transport to the Interim Storage Facility
한국방사성폐기물학회 학술대회
2017 .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
Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage
Nuclear Engineering and Technology
2017 .01
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
소형 수소저장물질 유효열전도도 측정장치의 신뢰성 평가
한국수소및신에너지학회논문집
2015 .10
0