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Validation of UNIST Monte Carlo code MCS using VERA progression problems
Nuclear Engineering and Technology
2020 .01
Application of TULIP/STREAM code in 2-D fast reactor core high-fidelity neutronic analysis
Nuclear Engineering and Technology
2019 .01
Verification and Validation of STREAM/RAST-K for PWR Analysis
Nuclear Engineering and Technology
2019 .01
MC21/CTF and VERA multiphysics solutions to VERA core physics benchmark progression problems 6 and 7
Nuclear Engineering and Technology
2017 .01
Simulations of BEAVRS benchmark cycle 2 depletion with MCS/CTF coupling system
Nuclear Engineering and Technology
2020 .01
Validation of MCS code for shielding calculation using SINBAD
Nuclear Engineering and Technology
2022 .09
Uncertainty quantification based on similarity analysis of reactor physics benchmark experiments for SFR using TRU metallic fuel
Nuclear Engineering and Technology
2024 .09
Transient full core analysis of PWR with multi-scale and multi-physics approach
Nuclear Engineering and Technology
2024 .03
Multi-Scale and Multi-Physics Approach to Safety Analysis of Nuclear Reactor
한국전산유체공학회 학술대회논문집
2022 .10
Application of a new neutronics/thermal-hydraulics coupled code for steady state analysis of light water reactors
Nuclear Engineering and Technology
2020 .08
Uncertainty and sensitivity analysis in reactivity-initiated accident fuel modeling: synthesis of organisation for economic co-operation and development (OECD)/nuclear energy agency (NEA) benchmark on reactivity-initiated accident codes phase-II
Nuclear Engineering and Technology
2018 .01
PILLAR: Integral test facility for LBE-cooled passive small modular reactor research and computational code benchmark
Nuclear Engineering and Technology
2021 .11
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
일반물리 교육을 위한 코딩 수업 연구
한국컴퓨터그래픽스학회 학술대회
2017 .07
Platform development for multi-physics coupling and uncertainty analysis based on a unified framework
Nuclear Engineering and Technology
2023 .05
Development and validation of multiphysics PWR core simulator KANT
Nuclear Engineering and Technology
2023 .06
Development and verification of a Monte Carlo two-step method for lead-based fast reactor neutronics analysis
Nuclear Engineering and Technology
2023 .06
소하천 하도설계를 위한 Stream Channel Design Program 개발
대한토목학회지
2019 .08
Physics-Based State of Charge and Energy Estimation Framework Using Physics-Informed Deep Learning Model
대한산업공학회 추계학술대회 논문집
2024 .10
CFD/RELAP5 Coupling Analysis of the ISP No. 43 Boron Dilution Experiment
Nuclear Engineering and Technology
2022 .01
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