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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
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
Overcoming the challenges of Monte Carlo depletion: Application to a material-testing reactor with the MCS code
Nuclear Engineering and Technology
2020 .09
On-the-Fly Estimation Strategy for Uncertainty Propagation in Two-Step Monte Carlo Calculation for Residual Radiation Analysis
Nuclear Engineering and Technology
2016 .06
Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis
Nuclear Engineering and Technology
2021 .09
Verification of a two-step code system MCS/RAST-F to fast reactor core analysis
Nuclear Engineering and Technology
2022 .05
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
A hybrid neutronics method with novel fission diffusion synthetic acceleration for criticality calculations
Nuclear Engineering and Technology
2023 .04
An assessment of the applicability of multigroup cross sections generated with Monte Carlo method for fast reactor analysis
Nuclear Engineering and Technology
2020 .12
Validation of MCS code for shielding calculation using SINBAD
Nuclear Engineering and Technology
2022 .09
Effects of the move towards Gen IV reactors in capacity expansion planning by total generation cost and environmental impact optimization
Nuclear Engineering and Technology
2021 .04
Domain decomposition for GPU-Based continuous energy Monte Carlo power reactor calculation
Nuclear Engineering and Technology
2020 .11
i4mC-NN: Identification of 4mC sites in Rosaceae Genome Using Neural Network Architecture With Multiple Encoding Schemes
제어로봇시스템학회 국제학술대회 논문집
2022 .11
국내 유명 MC들에 대한 음성 특징 분석
한국통신학회 학술대회논문집
2015 .06
Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation
Nuclear Engineering and Technology
2018 .01
신규 개발 저출력 연구용 원자로 구조물 집합체의 동특성 해석
대한기계학회 춘추학술대회
2018 .12
모듈러 공동주택의 MC설계기준 적용실태
대한건축학회 학술발표대회 논문집
2018 .10
MC 기법을 이용한 수소 탱크 충전 성능 향상에 관한 연구
한국수소및신에너지학회논문집
2023 .10
Cross section generation for a conceptual horizontal, compact high temperature gas reactor
Nuclear Engineering and Technology
2024 .03
Multi-Scale and Multi-Physics Approach to Safety Analysis of Nuclear Reactor
한국전산유체공학회 학술대회논문집
2022 .10
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