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Uncertainty analysis of UAM TMI-1 benchmark by STREAM/RAST-K
Nuclear Engineering and Technology
2024 .05
Development and validation of isotope prediction module for VVER spent nuclear fuel analysis
Nuclear Engineering and Technology
2024 .05
Development and validation of transient analysis module in nodal diffusion code RAST-V with Kalinin-3 coolant transient benchmark
Nuclear Engineering and Technology
2024 .06
RANS uncertainty quantification study On turbulent convection problems using artificial neural networks
한국전산유체공학회 학술대회논문집
2022 .10
Uncertainty Quantification of a Rotating Beam considering Parameter Random Fields
대한기계학회 춘추학술대회
2015 .05
A methodology for uncertainty quantifi cation and sensitivity analysis for responses subject to Monte Carlo uncertainty with application to fuel plate characteristics in the ATRC
Nuclear Engineering and Technology
2022 .03
Verification and Validation of STREAM/RAST-K for PWR Analysis
Nuclear Engineering and Technology
2019 .01
McCARD/MIG Stochastic sampling calculations for nuclear cross section sensitivity and uncertainty analysis
Nuclear Engineering and Technology
2022 .11
적합 직교 분해 및 다항식 혼돈 확장을 활용한 비침습 확률적 모델 축소 기법
대한기계학회 춘추학술대회
2021 .08
Verification of a two-step code system MCS/RAST-F to fast reactor core analysis
Nuclear Engineering and Technology
2022 .05
Establishment of DeCART/MIG stochastic sampling code system and Application to UAM and BEAVRS benchmarks
Nuclear Engineering and Technology
2023 .04
Uncertainty quantifi cation in decay heat calculation of spent nuclear fuel by STREAM/RAST-K
Nuclear Engineering and Technology
2021 .09
Analysis of VVER-1000 mock-up criticality experiments with nuclear data library ENDF/B-VIII.0 and Monte Carlo code MCS
Nuclear Engineering and Technology
2021 .01
Uncertainty quantification based on similarity analysis of reactor physics benchmark experiments for SFR using TRU metallic fuel
Nuclear Engineering and Technology
2024 .09
Neutronics design of VVER-1000 fuel assembly with burnable poison particles
Nuclear Engineering and Technology
2019 .01
Analyzing nuclear reactor simulation data and uncertainty with the group method of data handling
Nuclear Engineering and Technology
2020 .01
ASSESSMENT OF THE TiO2/WATER NANOFLUID EFFECTS ON HEAT TRANSFER CHARACTERISTICS IN VVER-1000 NUCLEAR REACTOR USING CFD MODELING
Nuclear Engineering and Technology
2015 .01
UAM 간 통신을 통한 UAM 3 차원 협력 측위 기법
한국통신학회 학술대회논문집
2022 .11
고도와 경로를 활용한 UAM 모니터링 시스템 개발
Proceedings of KIIT Conference
2023 .06
불확실성을 고려한 UAM 이륙 및 코리도 진입 방법에 대한 연구
한국항공우주학회 학술발표회 초록집
2023 .11
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