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The 'Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors' is a comprehensive guide focusing on the modeling and simulation aspects of nuclear reactor thermal hydraulics. Edited by Francesco D’Auria and Yassin A. Hassan, the book consolidates contributions from numerous researchers in the field. It emphasizes the intricacies of system codes, computational fluid dynamics, and the validation and verification processes crucial for nuclear reactor safety and design. The volume addresses the application of these methodologies in accident analysis, highlighting the best estimate plus uncertainty approach. This resource is aimed at professionals and researchers in nuclear engineering, providing detailed insights into the thermal hydraulic phenomena associated with nuclear reactors.

Thermal hydraulics. --- Nuclear reactors. --- Thermal hydraulics --- Nuclear reactors

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This eBook is a collection of articles from a Frontiers Research Topic. Frontiers Research Topics are very popular trademarks of the Frontiers Journals Series: they are collections of at least ten articles, all centered on a particular subject. With their unique mix of varied contributions from Original Research to Review Articles, Frontiers Research Topics unify the most influential researchers, the latest key findings and historical advances in a hot research area! Find out more on how to host your own Frontiers Research Topic or contribute to one as an author by contacting the Frontiers Editorial Office: frontiersin.org/about/contact

nuclear safety --- core coolant --- thermal hydraulics --- simulation --- nuclear power plant

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reactor systems design --- reactor thermal hydraulics --- next generation reactors and advanced reactors --- reactor control systems --- radiation application and protection --- radiation measurements --- Nuclear engineering --- Electrical engineering --- Nuclear engineering. --- Electrical engineering. --- Electric engineering --- Engineering --- Atomic power engineering --- Nuclear physics --- Nuclear energy

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In nuclear fusion technology, thermal-hydraulics is a key discipline employed in the design phase of the systems and components to demonstrate performance, and to ensure the reliability and their efficient and economical operation. ITER is in charge of investigating the transients of the engineering systems; this included safety analysis. The thermal-hydraulics is required for the design and analysis of the cooling and ancillary systems such as the blanket, the divertor, the cryogenic, and the balance of plant systems, as well as the tritium carrier, extraction and recovery systems. This Special Issue collects and documents the recent scientific advancements which include, but are not limited to: thermal-hydraulic analyses of systems and components, including magneto-hydrodynamics; safety investigations of systems and components; numerical models and code development and application; codes coupling methodology; code assessment and validation, including benchmarks; experimental infrastructures design and operation; experimental campaigns and investigations; scaling issue in experiments.

packing structure --- contact force --- porosity distribution --- tritium breeder pebble bed --- breeding blanket --- discrete element method --- DEMO --- primary heat transfer system --- balance of plant --- RELAP5 --- loss of flow accident --- once through steam generators --- DEMO-EU fusion reactor --- IFMIF-DONES facility --- lithium technology --- CFD --- thermo-fluid dynamics --- lead-lithium eutectic --- In-box LOCA --- HCLL TBS --- liquid metal blanket --- MHD benchmarking --- COMSOL multiphysics --- magneto-convection --- turbulent MHD --- large eddy simulations --- magnetohydrodynamics (MHD) --- MHD pressure drop --- system codes --- liquid metal technology --- WCLL BB --- small ESS --- transient --- Apros --- Magnetohydrodynamics --- heat transfer --- WCLL --- thermal hydraulic --- WLLC blanket --- CFETR --- wakes --- open channel flow --- experimental methods --- DONES --- fusion --- liquid lithium --- LOCA --- Melcor --- numeric coupling --- liquid metal blankets --- tritium --- corrosion --- convection --- turbulence --- WCLL blanket --- DCLL blanket --- WCLL-BB --- MELCOR --- PHTS --- safety analysis --- HCPB BB --- CRAFT --- blanket and divertor --- experiment plan --- water loop design --- DEMO blanket --- first wall --- ODS steel layer --- tungsten functionally graded coating --- experimental investigation --- EU-DEMO --- helium-cooled pebble bed --- thermal storage --- indirect coupled design --- energy balance --- power conversion system --- simulation --- gyrotron resonator --- multi-physic simulation --- thermal-hydraulics --- cooling --- mini-channels --- Raschig rings --- validation --- divertor --- plasma facing components --- thermal hydraulics --- SIMMER code --- RELAP5 code --- in-box LOCA --- WCLL breeding blanket --- LIFUS5/Mod3

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This revised text covers the fundamentals of thermodynamics required to understand electrical power generation systems and the application of these principles to nuclear reactor power plant systems. The book begins with fundamental definitions of units and dimensions, thermodynamic variables and the Laws of Thermodynamics progressing to sections on specific applications of the Brayton and Rankine cycles for power generation and projected reactor systems design issues. It is not a traditional general thermodynamics text, per se, but a practical thermodynamics volume intended to explain the fundamentals and apply them to the challenges facing actual nuclear power plants systems, where thermal hydraulics comes to play. There have been significant new findings for intercooled systems since the previous edition published and they will be included in this volume. New technology plans for using a Nuclear Air-Brayton as a storage system for a low carbon grid are presented along with updated component sizes and performance criteria for Small Modular Reactors. Written in a lucid, straight-forward style while retaining scientific rigor, the content is accessible to upper division undergraduate students and aimed at practicing engineers in nuclear power facilities and engineering scientists and technicians in industry, academic research groups, and national laboratories. The book is also a valuable resource for students and faculty in various engineering programs concerned with nuclear reactors. • Provides extensive coverage of thermal hydraulics with thermodynamics in nuclear reactors, from fundamentals to applications; • Reinforces fundamentals of fluid dynamics and heat transfer; thermal and hydraulic analysis of nuclear reactors, two-phase flow and boiling, compressible flow, stress analysis and energy conversion methods; • Includes detailed appendices that cover metric and English system units and conversions, detailed steam and gas tables, heat transfer properties and nuclear reactor system descriptions.

Energy. --- Nuclear energy. --- Applied mathematics. --- Engineering mathematics. --- Thermodynamics. --- Heat engineering. --- Heat transfer. --- Mass transfer. --- Fluid mechanics. --- Nuclear Energy. --- Engineering Thermodynamics, Heat and Mass Transfer. --- Appl.Mathematics/Computational Methods of Engineering. --- Engineering Fluid Dynamics. --- Nuclear reactors --- Thermal hydraulics. --- Thermohydraulics --- Reactor thermodynamics --- Hydraulics --- Liquids --- Thermodynamics --- Thermal properties --- Engineering. --- Hydraulic engineering. --- Mathematical and Computational Engineering. --- Engineering, Hydraulic --- Engineering --- Fluid mechanics --- Shore protection --- Engineering analysis --- Mathematical analysis --- Construction --- Industrial arts --- Technology --- Mathematics --- Heat transfer --- Thermal transfer --- Transmission of heat --- Energy transfer --- Heat --- Mechanical engineering --- Chemistry, Physical and theoretical --- Dynamics --- Mechanics --- Physics --- Heat-engines --- Quantum theory --- Hydromechanics --- Continuum mechanics --- Mass transport (Physics) --- Transport theory --- Atomic energy --- Atomic power --- Energy, Atomic --- Energy, Nuclear --- Nuclear power --- Power, Atomic --- Power, Nuclear --- Force and energy --- Nuclear physics --- Power resources --- Nuclear engineering --- Nuclear facilities --- Nuclear power plants