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Thermal-Hydraulics in Nuclear Fusion Technology: R&D and Applications
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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.
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Keywords
- Apros
- balance of plant
- blanket and divertor
- breeding blanket
- CFD
- CFETR
- Computing & information technology
- COMSOL Multiphysics
- contact force
- convection
- cooling
- Corrosion
- craft
- DCLL blanket
- DEMO
- DEMO blanket
- DEMO-EU fusion reactor
- discrete element method
- divertor
- Dones
- energy balance
- EU-DEMO
- experiment plan
- experimental investigation
- Experimental methods
- first wall
- fusion
- gyrotron resonator
- HCLL TBS
- HCPB BB
- heat transfer
- helium-cooled pebble bed
- IFMIF-DONES facility
- In-box LOCA
- indirect coupled design
- large eddy simulations
- lead-lithium eutectic
- LIFUS5/Mod3
- liquid lithium
- liquid metal blanket
- liquid metal blankets
- liquid metal technology
- lithium technology
- LOCA
- loss of flow accident
- magneto-convection
- magnetohydrodynamics
- Magnetohydrodynamics (MHD)
- Melcor
- MHD benchmarking
- MHD pressure drop
- mini-channels
- multi-physic simulation
- numeric coupling
- ODS steel layer
- once through steam generators
- open channel flow
- Operating Systems
- packing structure
- PHTS
- plasma facing components
- porosity distribution
- power conversion system
- primary heat transfer system
- Raschig rings
- RELAP5
- RELAP5 code
- safety analysis
- SIMMER code
- simulation
- small ESS
- system codes
- Thermal Hydraulic
- thermal hydraulics
- thermal storage
- thermal-hydraulics
- thermo-fluid dynamics
- transient
- Tritium
- tritium breeder pebble bed
- tungsten functionally graded coating
- Turbulence
- turbulent MHD
- Validation
- wakes
- water loop design
- WCLL
- WCLL BB
- WCLL blanket
- WCLL breeding blanket
- WCLL-BB
- WLLC blanket
Links
DOI: 10.3390/books978-3-0365-3033-8Editions