Thermal-Hydraulics in Nuclear Fusion Technology: R&D and Applications

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...

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Bibliographic Details
Format: eBook
Language:English
Published: Basel MDPI - Multidisciplinary Digital Publishing Institute 2022
Subjects:
CFD
Online Access:Open Access: DOAB: description of the publication
Open Access: DOAB, download the publication
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520 |a 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. 
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653 |a breeding blanket 
653 |a CFD 
653 |a CFETR 
653 |a COMSOL multiphysics 
653 |a contact force 
653 |a convection 
653 |a cooling 
653 |a corrosion 
653 |a CRAFT 
653 |a DCLL blanket 
653 |a DEMO 
653 |a DEMO blanket 
653 |a DEMO-EU fusion reactor 
653 |a discrete element method 
653 |a divertor 
653 |a DONES 
653 |a energy balance 
653 |a EU-DEMO 
653 |a experiment plan 
653 |a experimental investigation 
653 |a experimental methods 
653 |a first wall 
653 |a fusion 
653 |a gyrotron resonator 
653 |a HCLL TBS 
653 |a HCPB BB 
653 |a heat transfer 
653 |a helium-cooled pebble bed 
653 |a IFMIF-DONES facility 
653 |a in-box LOCA 
653 |a In-box LOCA 
653 |a indirect coupled design 
653 |a large eddy simulations 
653 |a lead-lithium eutectic 
653 |a LIFUS5/Mod3 
653 |a liquid lithium 
653 |a liquid metal blanket 
653 |a liquid metal blankets 
653 |a liquid metal technology 
653 |a lithium technology 
653 |a LOCA 
653 |a loss of flow accident 
653 |a magneto-convection 
653 |a Magnetohydrodynamics 
653 |a magnetohydrodynamics (MHD) 
653 |a Melcor 
653 |a MELCOR 
653 |a MHD benchmarking 
653 |a MHD pressure drop 
653 |a mini-channels 
653 |a multi-physic simulation 
653 |a numeric coupling 
653 |a ODS steel layer 
653 |a once through steam generators 
653 |a open channel flow 
653 |a packing structure 
653 |a PHTS 
653 |a plasma facing components 
653 |a porosity distribution 
653 |a power conversion system 
653 |a primary heat transfer system 
653 |a Raschig rings 
653 |a RELAP5 
653 |a RELAP5 code 
653 |a safety analysis 
653 |a SIMMER code 
653 |a simulation 
653 |a small ESS 
653 |a system codes 
653 |a thermal hydraulic 
653 |a thermal hydraulics 
653 |a thermal storage 
653 |a thermal-hydraulics 
653 |a thermo-fluid dynamics 
653 |a transient 
653 |a tritium 
653 |a tritium breeder pebble bed 
653 |a tungsten functionally graded coating 
653 |a turbulence 
653 |a turbulent MHD 
653 |a validation 
653 |a wakes 
653 |a water loop design 
653 |a WCLL 
653 |a WCLL BB 
653 |a WCLL blanket 
653 |a WCLL breeding blanket 
653 |a WCLL-BB 
653 |a WLLC blanket 
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