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The extended papers in this Special Issue cover the topics of smart energy, nuclear systems, and micro energy grids. In “Electrical Loads and Power Systems for the DEMO Nuclear Fusion Project” and “Energy Analysis for the Connection of the Nuclear Reactor DEMO to the European Electrical Grid”, the authors introduce a European DEMO project. In “Comparison and Design of Resonant Network Considering the Characteristics of a Plasma Generator” the authors present a theoretical analysis and experimental study on the resonant network of the power conditioning system (PCS). In “Techno-Economic Evaluation of Interconnected Nuclear-Renewable Micro Hybrid Energy Systems with Combined Heat and Power”, the authors conducted a sensitivity analysis to identify the impact of the different variables on the investigated systems. In “Fault Current Tracing and Identification via Machine Learning Considering Distributed Energy Resources in Distribution Networks”, the authors propose a current tracing method to model the single distribution feeder as several independent parallel connected virtual lines, with the result of tracing the detailed contribution of different current sources to the power line current. From the five extended papers, we observe that the SEGE is actively engaged in smart grid and green energy techniques. We hope that the readers enjoy this Special Issue.

plasma generator --- LCL network --- LCCL network --- phase compensation --- ZVS control --- current tracing --- fault current --- distributed energy resources --- network model --- nuclear power plant --- renewable energy --- hybrid energy system --- combined heat and power --- nuclear fusion --- tokamak --- generation power plant --- power system --- electrical transmission grid --- balance of plant --- DEMO --- electric loads --- plasma --- power flow --- power supply --- power systems

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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.

Computing & information technology --- Operating systems --- 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 --- 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

Choose an application

• Reference Manager
• EndNote
• RefWorks (Direct export to RefWorks)

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