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2018
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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Effect of Long-term Cooling on the Hydride Reorientation of Non-irradiated Zircaloy-4 Cladding Tube : 1M, 3M & 6M
한국방사성폐기물학회 학술대회
2019 .01
CY LED 기술을 활용한 자동차 리어램프의 혁신적 디자인과 ESG 기여
한국자동차공학회 춘계학술대회
2024 .06
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
LCD Color Filter용 Cy3 염료의 제조 및 특성 연구
전기전자재료학회논문지
2016 .01
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
Micro-cantilever Tests on Hydride Blister and Zirconium Matrix of Zircaloy-4 Cladding Tube
한국방사성폐기물학회 학술대회
2019 .01
비조사 Zircaloy-4 피복관의 링압축 고온 특성 평가
대한기계학회 춘추학술대회
2024 .11
Effects of Zr-hydride distribution of irradiated Zircaloy-3 cladding in RIA-simulating pellet-clad mechanical interaction testing
Nuclear Engineering and Technology
2018 .01
Measurement of Threshold Stress Intensity Factor of Delayed Hydride Cracking for Unirradiated Zircaloy-4 Cladding
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
ATP Recognition Based on the FRET from Organic Semiconducting Molecules to Cy3 Fluorophores
한국고분자학회 학술대회 연구논문 초록집
2021 .04
다양한 상대 양이온을 갖는 Cy3 염료의 제조 및 특성 연구
전기전자재료학회논문지
2015 .01
The effect of neutron irradiation on hydride reorientation and mechanical property degradation of zirconium alloy cladding
Nuclear Engineering and Technology
2017 .01
ITU의 5G 융합 표준화 및 신규 연구 회기(2020~2023년)를 위한 준비 사항 분석
한국통신학회 학술대회논문집
2019 .06
Influence of hydrogen concentration on burst parameters of Zircaloy-4 cladding tube under simulated loss-of-coolant accident
Nuclear Engineering and Technology
2020 .09
Theoretical models of threshold stress intensity factor and critical hydride length for delayed hydride cracking considering thermal stresses
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
Effect of a surface oxide-dispersion-strengthened layer on mechanical strength of Zircaloy-5 tubes
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
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