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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
비조사 Zircaloy-4 피복관의 링압축 고온 특성 평가
대한기계학회 춘추학술대회
2024 .11
Effect of a surface oxide-dispersion-strengthened layer on mechanical strength of Zircaloy-5 tubes
Nuclear Engineering and Technology
2018 .01
JRTR HWV의 zircaloy-4 내측쉘의 조사성장 거동 해석
대한기계학회 춘추학술대회
2016 .05
Hydrogen Content Effects on Delayed Hydride Cracking in Zircaloy-4 Cladding
한국방사성폐기물학회 학술대회
2018 .01
Circumferential steady-state creep test and analysis of Zircaloy-4 fuel cladding
Nuclear Engineering and Technology
2021 .07
Understanding the role of hydrogen on creep behaviour of Zircaloy-4 cladding tubes using nanoindentation
Nuclear Engineering and Technology
2020 .09
Effect of initial coating crack on the mechanical performance of surface-coated zircaloy cladding
Nuclear Engineering and Technology
2021 .04
Thermal creep behavior of CZ cladding under biaxial stress state
Nuclear Engineering and Technology
2020 .12
공간 균질화 된 나노초 레이저 빔을 활용한 지르코늄 합금(Zircaloy-4)의 표면 젖음성 변화 연구
대한용접·접합학회지
2022 .04
Measurement of Threshold Stress Intensity Factor of Delayed Hydride Cracking for Unirradiated Zircaloy-4 Cladding
한국방사성폐기물학회 학술대회
2019 .01
High-temperature oxidation behaviors of ZrSi2 and its coating on the surface of Zircaloy-4 tube by laser 3D printing
Nuclear Engineering and Technology
2020 .09
Influence of hydrogen concentration on burst parameters of Zircaloy-4 cladding tube under simulated loss-of-coolant accident
Nuclear Engineering and Technology
2020 .09
Characteristic of Zircaloy-fuel Mechanical Interaction in Failed Spent PWR Fuel
한국방사성폐기물학회 학술대회
2018 .01
Thermal creep effects of aluminum alloy cladding on the irradiation-induced mechanical behavior in U – 10Mo/Al monolithic fuel plates
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
Micro-cantilever Tests on Hydride Blister and Zirconium Matrix of Zircaloy-4 Cladding Tube
한국방사성폐기물학회 학술대회
2019 .01
Development of Cr cold spray – coated fuel cladding with enhanced accident tolerance
Nuclear Engineering and Technology
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
Electrochemical corrosion study of helium ions implanted Zircaloy-4 in chloride media
Nuclear Engineering and Technology
2021 .03
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