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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Adaptive energy group division in the few-group cross-section generation for full spectrum reactor modeling with deterministic method
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Verification and Validation of STREAM/RAST-K for PWR Analysis
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Development and verification of a Monte Carlo two-step method for lead-based fast reactor neutronics analysis
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Code Evaluation for Expansion Joint of a Research Reactor
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Whole-core analysis of Watts bar benchmark with three-dimensional MOC code STREAM3D
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Validation of UNIST Monte Carlo code MCS using VERA progression problems
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Validation of MCS code for shielding calculation using SINBAD
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Verification of a two-step code system MCS/RAST-F to fast reactor core analysis
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Design of a Mixed-Spectrum Reactor With Improved Proliferation Resistance for Long-Lived Applications
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Review of researches on coupled system and CFD codes
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TOP-MOUNTED IN-CORE INSTRUMENTATION : CURRENT STATUS AND TECHNICAL ISSUES
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An assessment of the applicability of multigroup cross sections generated with Monte Carlo method for fast reactor analysis
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Assessment of N-16 activity concentration in Bangladesh Atomic Energy Commission TRIGA Research Reactor
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Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation
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A simple method for estimating the major nuclide fractional ?ssion rates within light water and advanced gas cooled reactors
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Kinetics calculation of fast periodic pulsed reactors using MCNP6
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Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
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Transient Analysis of a Subcritical Reactor Core with a MOX-Fuel using the Birth-and-Death Model
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Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis
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