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Review of Design Requirements for SNF Dry Storage System
한국방사성폐기물학회 학술대회
2019 .01
A New Perspective of Hydride Re-orientation in SNF
한국방사성폐기물학회 학술대회
2017 .01
Requirements for Direct Radiation From SNF Dry Storage Casks
한국방사성폐기물학회 학술대회
2018 .01
Change in radiation characteristics outside the SNF storage container as an indicator of fuel rod cladding destruction
Nuclear Engineering and Technology
2021 .11
Measures for the Failure Evaluation of SNF Cladding During the Transportation
한국방사성폐기물학회 학술대회
2018 .01
Innovative technologies for spent fuel safe management at Ignalina channel-type reactors
Nuclear Engineering and Technology
2018 .01
Sensitivity Analysis of Thermal Conductivity on Thermal Dimensioning of SNF Direct Disposal System
한국방사성폐기물학회 학술대회
2019 .01
Spent Nuclear Fuel Safety Evaluation Methodology (SSEM) for Storage and Transportation
한국방사성폐기물학회 학술대회
2017 .01
Thermal Analysis of Transportation and Storage Cask of Spent Nuclear Fuel for Forced Gas Drying Condition
한국방사성폐기물학회 학술대회
2017 .01
Optimization of spent nuclear fuels per canister to improve the disposal efficiency of a deep geological repository in Korea
Nuclear Engineering and Technology
2022 .08
Preliminary data analysis of surrogate fuel-loaded road transportation tests under normal conditions of transport
Nuclear Engineering and Technology
2022 .11
Sensitivity of SNF transport cask response to uncertainty in properties of wood inside the impact limiter under drop accident conditions
Nuclear Engineering and Technology
2022 .10
Uncertainty quantification of PWR spent fuel due to nuclear data and modeling parameters
Nuclear Engineering and Technology
2021 .03
Thermal Safety Evaluation of Buffer for Preliminary Conceptual Design of SNF Disposal System
방사선산업학회지
2021 .09
Integrated risk assessment method for spent fuel road transportation accident under complex environment
Nuclear Engineering and Technology
2021 .02
설산하중조건에서의 사용후핵연료 처분용기 구조 건전성 평가
대한기계학회 춘추학술대회
2020 .12
Parametric study on the structural response of a high burnup spent nuclear fuel rod under drop impact considering post-irradiated fuel conditions
Nuclear Engineering and Technology
2020 .01
Structural Integrity Evaluation of Spent Nuclear Fuel Assembly Under Normal Transportation Drop Conditions
한국방사성폐기물학회 학술대회
2017 .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
Reprocessing of simulated voloxidized uranium–oxide SNF in the CARBEX process
Nuclear Engineering and Technology
2019 .01
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