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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
BEAVRS benchmark analyses by DeCART stand-alone calculations and comparison with DeCART/MATRA multi-physics coupling calculations
Nuclear Engineering and Technology
2020 .09
Establishment of DeCART/MIG stochastic sampling code system and Application to UAM and BEAVRS benchmarks
Nuclear Engineering and Technology
2023 .04
MULTIT-PHYSICS ANALYSIS OF NUCLEAR REACTOR USING CUPID/DeCART
한국전산유체공학회 학술대회논문집
2017 .11
Improvement and application of DeCART/MUSAD for uncertainty analysis of HTGR neutronic parameters
Nuclear Engineering and Technology
2020 .01
고온가스로 흑연 블록의 락킹 거동 전산 모사
대한기계학회 춘추학술대회
2015 .11
Cross section generation for a conceptual horizontal, compact high temperature gas reactor
Nuclear Engineering and Technology
2024 .03
고온가스로 내진해석 프로그램을 이용한 단일 컬럼 강제 진동 벤치마크 테스트
대한기계학회 춘추학술대회
2016 .12
고온가스로와 연계한 메탄 수증기 개질 수소생산 공정의 경제성 및 파급효과 추정
대한설비관리학회지
2019 .01
Processing and benchmarking of evaluated nuclear data file/b-viii.0β4 cross-section library by analysis of a series of critical experimental benchmark using the monte carlo code MCNP(X) and NJOY2016
Nuclear Engineering and Technology
2017 .01
[신기술 정보] 차세대 원자로: VHTR & HTGR
기계저널
2023 .04
McCARD/MIG Stochastic sampling calculations for nuclear cross section sensitivity and uncertainty analysis
Nuclear Engineering and Technology
2022 .11
A response matrix method for the refi ned Analytic Function Expansion Nodal (AFEN) method in the twodimensional hexagonal geometry and its numerical performance
Nuclear Engineering and Technology
2020 .11
Validation of nuclide depletion capabilities in Monte Carlo code MCS
Nuclear Engineering and Technology
2020 .09
Application of TULIP/STREAM code in 2-D fast reactor core high-fidelity neutronic analysis
Nuclear Engineering and Technology
2019 .01
Current Status of ACE Format Libraries for MCNP at Nuclear Data Center of KAERI
방사선방어학회지
2016 .01
Whole-core analysis of Watts bar benchmark with three-dimensional MOC code STREAM3D
Nuclear Engineering and Technology
2024 .08
Interpretation of two SINBAD photon-leakage benchmarks with nuclear library ENDF/B-VIII.0 and Monte Carlo code MCS
Nuclear Engineering and Technology
2020 .01
Numerical study of the flow and heat transfer characteristics in a scale model of the vessel cooling system for the HTTR
Nuclear Engineering and Technology
2024 .04
점진적 코드 개선을 위한 AST 기반의 코드 특징 추출 방법
대한전자공학회 학술대회
2024 .06
An inter-comparison between ENDF/B-VIII.0-NECP-Atlas and ENDF/B-VIII.0-NJOY results for criticality safety benchmarks and benchmarks on the reactivity temperature coefficient
Nuclear Engineering and Technology
2021 .08
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