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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Study of fission gas products effect on thermal hydraulics of the WWER1000 with enhanced subchannel method
Advances in energy research
2017 .01
Study on an open fuel cycle of IVG.1M research reactor operating with LEU-fuel
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Loading pattern optimization of VVER-1000 reactor core based on the discrete golden eagle optimization algorithm
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Evaluation of the Middle Part of the Nuclear Fuel Cycle
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2016 .01
Equilibrium Cycle Loading Pattern Optimization for APR1400 using Simulated Annealing Algorithm
에너지공학
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Investigating Heavy Water Zero Power Reactors with a New Core Configuration Based on Experiment and Calculation Results
Nuclear Engineering and Technology
2017 .01
Segmented mandrel tests of as-received and hydrogenated WWER fuel cladding tubes
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2021 .09
Nuclear Fuel Batch Optimization for Extra Long Equilibrium Core Design of APR-1400
에너지공학
2023 .06
Loading pattern optimization using simulated annealing and binary machine learning pre-screening
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Neutronics analysis of TRIGA Mark II research reactor
Nuclear Engineering and Technology
2018 .01
[프로젝트 리포트] 파크원
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Conceptual design of a high neutron fl ux research reactor core with low enriched uranium fuel and low plutonium production
Nuclear Engineering and Technology
2020 .01
자동차 5-cycle 연비 시험방법에 따른 5-cycle 보정식 적용 검증 연구
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2021 .11
Design of a Mixed-Spectrum Reactor With Improved Proliferation Resistance for Long-Lived Applications
방사성폐기물학회지
2018 .01
Impact of fuel temperature on nuclear core design calculations
Nuclear Engineering and Technology
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Core analysis of accident tolerant fuel cladding for SMART reactor under normal operation and rod ejection accident using DRAGON and PARCS
Nuclear Engineering and Technology
2021 .03
Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation
Nuclear Engineering and Technology
2018 .01
Design of a direct-cycle supercritical CO2 nuclear reactor with heavy water moderation
Nuclear Engineering and Technology
2022 .03
Adaptive energy group division in the few-group cross-section generation for full spectrum reactor modeling with deterministic method
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Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide
Nuclear Engineering and Technology
2020 .01
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