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05/00656 Validation of coupled neutronic/thermal-hydraulic code RELAP5-3D for RBMK-1500 reactor analysis application

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Key concepts: RBMK, Decay heat, Nuclear engineering, Nuclear reactor core, Control rod, Thermal hydraulics, Water cooling, Environmental science

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05/00656 Validation of coupled neutronic/thermal-hydraulic code RELAP5-3D for RBMK-1500 reactor analysis application — Research Paper | ScholarLens