TY  - GEN
AU  - Del Nevo,Alessandro
AU  - Eboli,Marica
AU  - Del Nevo,Alessandro
AU  - Eboli,Marica
TI  - Thermal-Hydraulics in Nuclear Fusion Technology: R&D and Applications
SN  - books978-3-0365-3033-8
PY  - 2022///
CY  - Basel
PB  - MDPI - Multidisciplinary Digital Publishing Institute
KW  - Computing & information technology
KW  - bicssc
KW  - Operating systems
KW  - packing structure
KW  - contact force
KW  - porosity distribution
KW  - tritium breeder pebble bed
KW  - breeding blanket
KW  - discrete element method
KW  - DEMO
KW  - primary heat transfer system
KW  - balance of plant
KW  - RELAP5
KW  - loss of flow accident
KW  - once through steam generators
KW  - DEMO-EU fusion reactor
KW  - IFMIF-DONES facility
KW  - lithium technology
KW  - CFD
KW  - thermo-fluid dynamics
KW  - lead-lithium eutectic
KW  - In-box LOCA
KW  - HCLL TBS
KW  - liquid metal blanket
KW  - MHD benchmarking
KW  - COMSOL multiphysics
KW  - magneto-convection
KW  - turbulent MHD
KW  - large eddy simulations
KW  - magnetohydrodynamics (MHD)
KW  - MHD pressure drop
KW  - system codes
KW  - liquid metal technology
KW  - WCLL BB
KW  - small ESS
KW  - transient
KW  - Apros
KW  - Magnetohydrodynamics
KW  - heat transfer
KW  - WCLL
KW  - thermal hydraulic
KW  - WLLC blanket
KW  - CFETR
KW  - wakes
KW  - open channel flow
KW  - experimental methods
KW  - DONES
KW  - fusion
KW  - liquid lithium
KW  - LOCA
KW  - Melcor
KW  - numeric coupling
KW  - liquid metal blankets
KW  - tritium
KW  - corrosion
KW  - convection
KW  - turbulence
KW  - WCLL blanket
KW  - DCLL blanket
KW  - WCLL-BB
KW  - MELCOR
KW  - PHTS
KW  - safety analysis
KW  - HCPB BB
KW  - CRAFT
KW  - blanket and divertor
KW  - experiment plan
KW  - water loop design
KW  - DEMO blanket
KW  - first wall
KW  - ODS steel layer
KW  - tungsten functionally graded coating
KW  - experimental investigation
KW  - EU-DEMO
KW  - helium-cooled pebble bed
KW  - thermal storage
KW  - indirect coupled design
KW  - energy balance
KW  - power conversion system
KW  - simulation
KW  - gyrotron resonator
KW  - multi-physic simulation
KW  - thermal-hydraulics
KW  - cooling
KW  - mini-channels
KW  - Raschig rings
KW  - validation
KW  - divertor
KW  - plasma facing components
KW  - thermal hydraulics
KW  - SIMMER code
KW  - RELAP5 code
KW  - in-box LOCA
KW  - WCLL breeding blanket
KW  - LIFUS5/Mod3
N1  - Open Access
N2  - 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
UR  - https://mdpi.com/books/pdfview/book/4997
UR  - https://directory.doabooks.org/handle/20.500.12854/79612
ER  -