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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
TRIGA-II 연구용 원자로의 출력제어
제어로봇시스템학회 국내학술대회 논문집
2017 .05
Sensitivity and Uncertainty quantification of neutronic integral data in the TRIGA Mark II Research Reactor
Nuclear Engineering and Technology
2022 .02
Analysis of the first core of the Indonesian multipurpose research reactor RSG-GAS using the Serpent Monte Carlo code and the ENDF/BVIII.0 nuclear data library
Nuclear Engineering and Technology
2020 .12
JSI TRIGA fuel rod reactivity worth experiments for validation of Serpent-2 and RAPID fuel burnup calculations
Nuclear Engineering and Technology
2024 .08
Influence of nuclear data library on neutronics benchmark of China experimental fast reactor start-up tests
Nuclear Engineering and Technology
2022 .10
Investigating Heavy Water Zero Power Reactors with a New Core Configuration Based on Experiment and Calculation Results
Nuclear Engineering and Technology
2017 .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
Neutronics analysis of JSI TRIGA Mark II reactor benchmark experiments with SuperMC3.3
Nuclear Engineering and Technology
2019 .01
Analysis of the CREOLE experiment on the reactivity temperature coefficient of the UO2 light water moderated lattices using Monte Carlo transport calculations and ENDF/B-VII.1 nuclear data library
Nuclear Engineering and Technology
2020 .01
Supercritical CO2-cooled fast reactor and cold shutdown system for ship propulsion
Nuclear Engineering and Technology
2024 .03
Validation of a New Design of Tellurium Dioxide-Irradiated Target
Nuclear Engineering and Technology
2016 .01
Application of TULIP/STREAM code in 2-D fast reactor core high-fidelity neutronic analysis
Nuclear Engineering and Technology
2019 .01
Development and verification of a Monte Carlo two-step method for lead-based fast reactor neutronics analysis
Nuclear Engineering and Technology
2023 .06
Assessment of N-16 activity concentration in Bangladesh Atomic Energy Commission TRIGA Research Reactor
Nuclear Engineering and Technology
2018 .01
Evaluation of neutronics parameters during RSG-GAS commissioning by using Monte Carlo code
Nuclear Engineering and Technology
2023 .05
Neutronic analysis of control rod effect on safety parameters in Tehran Research Reactor
Nuclear Engineering and Technology
2018 .01
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
시뮬레이션 데이터 생성을 통한 기계학습 기반 원자로 노심 이상 탐지 방법론
대한산업공학회지
2021 .04
Current Status of ACE Format Libraries for MCNP at Nuclear Data Center of KAERI
방사선방어학회지
2016 .01
Validation of UNIST Monte Carlo code MCS using VERA progression problems
Nuclear Engineering and Technology
2020 .01
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