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dc.contributor.editorDel Nevo, Alessandro
dc.contributor.editorEboli, Marica
dc.date.accessioned2022-03-21T16:28:06Z
dc.date.available2022-03-21T16:28:06Z
dc.date.issued2022
dc.identifierONIX_20220321_9783036530321_48
dc.identifier.urihttps://directory.doabooks.org/handle/20.500.12854/79612
dc.description.abstractIn 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.
dc.languageEnglish
dc.subject.classificationthema EDItEUR::U Computing and Information Technologyen_US
dc.subject.classificationthema EDItEUR::U Computing and Information Technology::UL Operating systemsen_US
dc.subject.otherpacking structure
dc.subject.othercontact force
dc.subject.otherporosity distribution
dc.subject.othertritium breeder pebble bed
dc.subject.otherbreeding blanket
dc.subject.otherdiscrete element method
dc.subject.otherDEMO
dc.subject.otherprimary heat transfer system
dc.subject.otherbalance of plant
dc.subject.otherRELAP5
dc.subject.otherloss of flow accident
dc.subject.otheronce through steam generators
dc.subject.otherDEMO-EU fusion reactor
dc.subject.otherIFMIF-DONES facility
dc.subject.otherlithium technology
dc.subject.otherCFD
dc.subject.otherthermo-fluid dynamics
dc.subject.otherlead-lithium eutectic
dc.subject.otherIn-box LOCA
dc.subject.otherHCLL TBS
dc.subject.otherliquid metal blanket
dc.subject.otherMHD benchmarking
dc.subject.otherCOMSOL multiphysics
dc.subject.othermagneto-convection
dc.subject.otherturbulent MHD
dc.subject.otherlarge eddy simulations
dc.subject.othermagnetohydrodynamics (MHD)
dc.subject.otherMHD pressure drop
dc.subject.othersystem codes
dc.subject.otherliquid metal technology
dc.subject.otherWCLL BB
dc.subject.othersmall ESS
dc.subject.othertransient
dc.subject.otherApros
dc.subject.otherMagnetohydrodynamics
dc.subject.otherheat transfer
dc.subject.otherWCLL
dc.subject.otherthermal hydraulic
dc.subject.otherWLLC blanket
dc.subject.otherCFETR
dc.subject.otherwakes
dc.subject.otheropen channel flow
dc.subject.otherexperimental methods
dc.subject.otherDONES
dc.subject.otherfusion
dc.subject.otherliquid lithium
dc.subject.otherLOCA
dc.subject.otherMelcor
dc.subject.othernumeric coupling
dc.subject.otherliquid metal blankets
dc.subject.othertritium
dc.subject.othercorrosion
dc.subject.otherconvection
dc.subject.otherturbulence
dc.subject.otherWCLL blanket
dc.subject.otherDCLL blanket
dc.subject.otherWCLL-BB
dc.subject.otherMELCOR
dc.subject.otherPHTS
dc.subject.othersafety analysis
dc.subject.otherHCPB BB
dc.subject.otherCRAFT
dc.subject.otherblanket and divertor
dc.subject.otherexperiment plan
dc.subject.otherwater loop design
dc.subject.otherDEMO blanket
dc.subject.otherfirst wall
dc.subject.otherODS steel layer
dc.subject.othertungsten functionally graded coating
dc.subject.otherexperimental investigation
dc.subject.otherEU-DEMO
dc.subject.otherhelium-cooled pebble bed
dc.subject.otherthermal storage
dc.subject.otherindirect coupled design
dc.subject.otherenergy balance
dc.subject.otherpower conversion system
dc.subject.othersimulation
dc.subject.othergyrotron resonator
dc.subject.othermulti-physic simulation
dc.subject.otherthermal-hydraulics
dc.subject.othercooling
dc.subject.othermini-channels
dc.subject.otherRaschig rings
dc.subject.othervalidation
dc.subject.otherdivertor
dc.subject.otherplasma facing components
dc.subject.otherthermal hydraulics
dc.subject.otherSIMMER code
dc.subject.otherRELAP5 code
dc.subject.otherin-box LOCA
dc.subject.otherWCLL breeding blanket
dc.subject.otherLIFUS5/Mod3
dc.titleThermal-Hydraulics in Nuclear Fusion Technology: R&D and Applications
dc.typebook
oapen.identifier.doi10.3390/books978-3-0365-3033-8
oapen.relation.isPublishedBy46cabcaa-dd94-4bfe-87b4-55023c1b36d0
oapen.relation.isbn9783036530321
oapen.relation.isbn9783036530338
oapen.pages422
oapen.place.publicationBasel


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