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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
The Effects of Cross-Section Openings on the Chlorination Reaction Rate of ZIRLO Cladding Hulls
방사성폐기물학회지
2015 .01
Effects of hydride precipitation on the mechanical property of cold worked zirconium alloys in fully recrystallized condition
Nuclear Engineering and Technology
2020 .01
Effect of Long-term Cooling on the Hydride Reorientation of Non-irradiated Zircaloy-4 Cladding Tube : 1M, 3M & 6M
한국방사성폐기물학회 학술대회
2019 .01
ZIRLO 판재의 응력 및 변형률 기반 다양한 성형한계 판단 기준
한국자동차공학회 지회 학술대회 논문집
2020 .06
염소화 TGA 장치를 이용한 ZIRLO 피복관의 단면 개방 영향 분석
한국방사성폐기물학회 학술대회
2015 .01
Behavior of Microstructure and Corrosion Properties of Zirlo-Cr-Si-NM Metal Waste Form Alloys by Change of Si Content
한국방사성폐기물학회 학술대회
2017 .01
Effects on SS304 Contents to Corrosion Properties of ZIRLO-SS304-INCONEL718-NM Alloy for Long-Term Disposal
한국방사성폐기물학회 학술대회
2017 .01
Effects of Hydride Re-orientation and Hydride Rim on Fracture Energy of Zircaloy-4 Cladding
한국방사성폐기물학회 학술대회
2018 .01
Temperature-dependent axial mechanical properties of Zircaloy-4 with various hydrogen amounts and hydride orientations
Nuclear Engineering and Technology
2022 .05
Three-dimensional Numerical Simulation of Hydrogen-induced Multi-field Coupling Behavior in Cracked Zircaloy Cladding Tubes
Nuclear Engineering and Technology
2019 .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
ZIRLO의 표면 처리 방법에 따른 알칼리 실리케이트 내열 코팅의 증진
대한기계학회 춘추학술대회
2020 .12
The effect of neutron irradiation on hydride reorientation and mechanical property degradation of zirconium alloy cladding
Nuclear Engineering and Technology
2017 .01
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
Microstructure and Corrosion Properties of Zirlo-Inconel718-SS304-NM Metal Waste Form Alloys for Improving Stability of Metal Waste Generated by Pyro-Process and Long-term Disposal Stability
한국방사성폐기물학회 학술대회
2017 .01
Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage
Nuclear Engineering and Technology
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
소형 수소저장물질 유효열전도도 측정장치의 신뢰성 평가
한국수소및신에너지학회논문집
2015 .10
Development and testing of the hydrogen behavior tool for Falcon – HYPE
Nuclear Engineering and Technology
2024 .02
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