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Development of risk assessment framework and the case study for a spent fuel pool of a nuclear power plant
Nuclear Engineering and Technology
2021 .04
Experimental and theoretical justification of passive heat removal system for irradiated fuel assemblies of the nuclear research reactor in a spent fuel pool
Nuclear Engineering and Technology
2023 .06
Validation of spent nuclear fuel decay heat calculation by a two-step method
Nuclear Engineering and Technology
2021 .01
Uncertainty quantifi cation in decay heat calculation of spent nuclear fuel by STREAM/RAST-K
Nuclear Engineering and Technology
2021 .09
Machine learning of LWR spent nuclear fuel assembly decay heat measurements
Nuclear Engineering and Technology
2021 .11
Large Scale Experiments Simulating Hydrogen Distribution in Spent Fuel Pool Building During a Hypothetical fuel Uncovery Accident Scenario
Nuclear Engineering and Technology
2016 .01
Analysis on short-term decay heat after shutdown during load-follow operation with seasonal and daily scenarios
Nuclear Engineering and Technology
2022 .10
Evaluation of Spent Nuclear Fuel Transshipment for Kori Unit 1 during Decommissioning
한국방사성폐기물학회 학술대회
2016 .01
Process Development for Kori Unit 1 Reactor Vessel Segmentation
한국방사성폐기물학회 학술대회
2018 .01
냉각기능상실사고 시 사용후핵연료 저장조의 열수력적 거동 특성
대한기계학회 춘추학술대회
2016 .12
Comparison of CFD Analysis Methodology for SFP Cooling Performance Evaluation
한국방사성폐기물학회 학술대회
2018 .01
Study on Segmentation Plan for Kori Unit 1 Reactor Vessel Internal
한국방사성폐기물학회 학술대회
2018 .01
Discussion on Non-fuel Waste Treatment in Connection With Dismantlement of Kori Unit 1
한국방사성폐기물학회 학술대회
2017 .01
Simulation-Based Evaluation for the Dismantling Scenario of the Reactor Vessel at Kori Unit 1
한국방사성폐기물학회 학술대회
2017 .01
Structural Integrity Evaluation of Spent Nuclear Fuel Assembly Under Normal Transportation Drop Conditions
한국방사성폐기물학회 학술대회
2017 .01
Conceptual Design for Kori Unit 1 Reactor Vessel and Internal Segmentation Process
한국방사성폐기물학회 학술대회
2017 .01
Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules
Nuclear Engineering and Technology
2021 .09
A Study for Dismantling Method of Bio-shield in Kori Unit 1 Nuclear Power Plant
한국방사성폐기물학회 학술대회
2019 .01
Status of Development of Final Decommissioning Plan for Kori Unit 1
한국방사성폐기물학회 학술대회
2019 .01
Study on Dismantling Scenario for Large Components of Kori Unit 1
한국방사성폐기물학회 학술대회
2018 .01
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