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THERMAL HYDRAULIC MODELS FOR NEUTRONIC AND THERMALY HYDRAULIC FEEDBACK IN CITVAP CODE
Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core
A coupled neutronic and thermal-hydraulic model for ALFRED
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Frontiers Neutronics and Thermal Hydraulics Analysis of a Conceptual Ultra-High Temperature MHD Cermet Fuel Core for Nuclear Electric Propulsion
Energies, Free Full-Text