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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Development and verification of a Monte Carlo two-step method for lead-based fast reactor neutronics analysis
Nuclear Engineering and Technology
2023 .06
MC21/CTF and VERA multiphysics solutions to VERA core physics benchmark progression problems 6 and 7
Nuclear Engineering and Technology
2017 .01
Overcoming the challenges of Monte Carlo depletion: Application to a material-testing reactor with the MCS code
Nuclear Engineering and Technology
2020 .09
Validation of MCS code for shielding calculation using SINBAD
Nuclear Engineering and Technology
2022 .09
Whole-core analysis of Watts bar benchmark with three-dimensional MOC code STREAM3D
Nuclear Engineering and Technology
2024 .08
Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis
Nuclear Engineering and Technology
2021 .09
Application of TULIP/STREAM code in 2-D fast reactor core high-fidelity neutronic analysis
Nuclear Engineering and Technology
2019 .01
TOP-MOUNTED IN-CORE INSTRUMENTATION : CURRENT STATUS AND TECHNICAL ISSUES
에너지공학
2015 .06
Verification of a two-step code system MCS/RAST-F to fast reactor core analysis
Nuclear Engineering and Technology
2022 .05
Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation
Nuclear Engineering and Technology
2018 .01
Verification and Validation of STREAM/RAST-K for PWR Analysis
Nuclear Engineering and Technology
2019 .01
On-the-Fly Estimation Strategy for Uncertainty Propagation in Two-Step Monte Carlo Calculation for Residual Radiation Analysis
Nuclear Engineering and Technology
2016 .06
State-Space Model Predictive Control Method for Core Power Control in Pressurized Water Reactor Nuclear Power Stations
Nuclear Engineering and Technology
2017 .01
Multi-Scale and Multi-Physics Approach to Safety Analysis of Nuclear Reactor
한국전산유체공학회 학술대회논문집
2022 .10
Simulations of BEAVRS benchmark cycle 2 depletion with MCS/CTF coupling system
Nuclear Engineering and Technology
2020 .01
A hybrid neutronics method with novel fission diffusion synthetic acceleration for criticality calculations
Nuclear Engineering and Technology
2023 .04
Adaptive energy group division in the few-group cross-section generation for full spectrum reactor modeling with deterministic method
Nuclear Engineering and Technology
2024 .06
Validation of nuclide depletion capabilities in Monte Carlo code MCS
Nuclear Engineering and Technology
2020 .09
MC 기법을 이용한 수소 탱크 충전 성능 향상에 관한 연구
한국수소및신에너지학회논문집
2023 .10
국내 유명 MC들에 대한 음성 특징 분석
한국통신학회 학술대회논문집
2015 .06
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