LEADER 05319nam 2201489z- 450 001 9910557612603321 005 20231214133051.0 035 $a(CKB)5400000000045276 035 $a(oapen)https://directory.doabooks.org/handle/20.500.12854/79612 035 $a(EXLCZ)995400000000045276 100 $a20202203d2022 |y 0 101 0 $aeng 135 $aurmn|---annan 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 10$aThermal-Hydraulics in Nuclear Fusion Technology: R&D and Applications 210 $aBasel$cMDPI - Multidisciplinary Digital Publishing Institute$d2022 215 $a1 electronic resource (422 p.) 311 $a3-0365-3032-0 311 $a3-0365-3033-9 330 $aIn 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. 517 $aThermal-Hydraulics in Nuclear Fusion Technology 606 $aComputing & information technology$2bicssc 606 $aOperating systems$2bicssc 610 $apacking structure 610 $acontact force 610 $aporosity distribution 610 $atritium breeder pebble bed 610 $abreeding blanket 610 $adiscrete element method 610 $aDEMO 610 $aprimary heat transfer system 610 $abalance of plant 610 $aRELAP5 610 $aloss of flow accident 610 $aonce through steam generators 610 $aDEMO-EU fusion reactor 610 $aIFMIF-DONES facility 610 $alithium technology 610 $aCFD 610 $athermo-fluid dynamics 610 $alead-lithium eutectic 610 $aIn-box LOCA 610 $aHCLL TBS 610 $aliquid metal blanket 610 $aMHD benchmarking 610 $aCOMSOL multiphysics 610 $amagneto-convection 610 $aturbulent MHD 610 $alarge eddy simulations 610 $amagnetohydrodynamics (MHD) 610 $aMHD pressure drop 610 $asystem codes 610 $aliquid metal technology 610 $aWCLL BB 610 $asmall ESS 610 $atransient 610 $aApros 610 $aMagnetohydrodynamics 610 $aheat transfer 610 $aWCLL 610 $athermal hydraulic 610 $aWLLC blanket 610 $aCFETR 610 $awakes 610 $aopen channel flow 610 $aexperimental methods 610 $aDONES 610 $afusion 610 $aliquid lithium 610 $aLOCA 610 $aMelcor 610 $anumeric coupling 610 $aliquid metal blankets 610 $atritium 610 $acorrosion 610 $aconvection 610 $aturbulence 610 $aWCLL blanket 610 $aDCLL blanket 610 $aWCLL-BB 610 $aMELCOR 610 $aPHTS 610 $asafety analysis 610 $aHCPB BB 610 $aCRAFT 610 $ablanket and divertor 610 $aexperiment plan 610 $awater loop design 610 $aDEMO blanket 610 $afirst wall 610 $aODS steel layer 610 $atungsten functionally graded coating 610 $aexperimental investigation 610 $aEU-DEMO 610 $ahelium-cooled pebble bed 610 $athermal storage 610 $aindirect coupled design 610 $aenergy balance 610 $apower conversion system 610 $asimulation 610 $agyrotron resonator 610 $amulti-physic simulation 610 $athermal-hydraulics 610 $acooling 610 $amini-channels 610 $aRaschig rings 610 $avalidation 610 $adivertor 610 $aplasma facing components 610 $athermal hydraulics 610 $aSIMMER code 610 $aRELAP5 code 610 $ain-box LOCA 610 $aWCLL breeding blanket 610 $aLIFUS5/Mod3 615 7$aComputing & information technology 615 7$aOperating systems 700 $aDel Nevo$b Alessandro$4edt$01319357 702 $aEboli$b Marica$4edt 702 $aDel Nevo$b Alessandro$4oth 702 $aEboli$b Marica$4oth 906 $aBOOK 912 $a9910557612603321 996 $aThermal-Hydraulics in Nuclear Fusion Technology: R&D and Applications$93033819 997 $aUNINA