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...
שמור ב:
| פורמט: | Online |
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| שפה: | אנגלית |
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MDPI - Multidisciplinary Digital Publishing Institute
2022
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| נושאים: | |
| גישה מקוונת: | ONIX_20220321_9783036530321_48 |
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| _version_ | 1869528850628608000 |
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| collection | Directory of Open Access Books |
| description | 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. |
| format | Online |
| id | doab-20.500.12854ir-79612 |
| institution | Directory of Open Access Books |
| language | eng |
| publishDate | 2022 |
| publishDateRange | 2022 |
| publishDateSort | 2022 |
| publisher | MDPI - Multidisciplinary Digital Publishing Institute |
| publisherStr | MDPI - Multidisciplinary Digital Publishing Institute |
| record_format | ojs |
| spelling | doab-20.500.12854ir-796122024-04-14T10:29:06Z Thermal-Hydraulics in Nuclear Fusion Technology: R&D and Applications Del Nevo, Alessandro Eboli, Marica packing structure contact force porosity distribution tritium breeder pebble bed breeding blanket discrete element method DEMO primary heat transfer system balance of plant RELAP5 loss of flow accident once through steam generators DEMO-EU fusion reactor IFMIF-DONES facility lithium technology CFD thermo-fluid dynamics lead-lithium eutectic In-box LOCA HCLL TBS liquid metal blanket MHD benchmarking COMSOL multiphysics magneto-convection turbulent MHD large eddy simulations magnetohydrodynamics (MHD) MHD pressure drop system codes liquid metal technology WCLL BB small ESS transient Apros Magnetohydrodynamics heat transfer WCLL thermal hydraulic WLLC blanket CFETR wakes open channel flow experimental methods DONES fusion liquid lithium LOCA Melcor numeric coupling liquid metal blankets tritium corrosion convection turbulence WCLL blanket DCLL blanket WCLL-BB MELCOR PHTS safety analysis HCPB BB CRAFT blanket and divertor experiment plan water loop design DEMO blanket first wall ODS steel layer tungsten functionally graded coating experimental investigation EU-DEMO helium-cooled pebble bed thermal storage indirect coupled design energy balance power conversion system simulation gyrotron resonator multi-physic simulation thermal-hydraulics cooling mini-channels Raschig rings validation divertor plasma facing components thermal hydraulics SIMMER code RELAP5 code in-box LOCA WCLL breeding blanket LIFUS5/Mod3 thema EDItEUR::U Computing and Information Technology thema EDItEUR::U Computing and Information Technology::UL Operating systems 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. 2022-03-21T16:28:06Z 2022-03-21T16:28:06Z 2022 book ONIX_20220321_9783036530321_48 9783036530321 9783036530338 https://directory.doabooks.org/handle/20.500.12854/79612 eng image/jpeg Attribution 4.0 International https://mdpi.com/books/pdfview/book/4997 https://mdpi.com/books/pdfview/book/4997 MDPI - Multidisciplinary Digital Publishing Institute 10.3390/books978-3-0365-3033-8 10.3390/books978-3-0365-3033-8 46cabcaa-dd94-4bfe-87b4-55023c1b36d0 9783036530321 9783036530338 422 Basel open access |
| spellingShingle | packing structure contact force porosity distribution tritium breeder pebble bed breeding blanket discrete element method DEMO primary heat transfer system balance of plant RELAP5 loss of flow accident once through steam generators DEMO-EU fusion reactor IFMIF-DONES facility lithium technology CFD thermo-fluid dynamics lead-lithium eutectic In-box LOCA HCLL TBS liquid metal blanket MHD benchmarking COMSOL multiphysics magneto-convection turbulent MHD large eddy simulations magnetohydrodynamics (MHD) MHD pressure drop system codes liquid metal technology WCLL BB small ESS transient Apros Magnetohydrodynamics heat transfer WCLL thermal hydraulic WLLC blanket CFETR wakes open channel flow experimental methods DONES fusion liquid lithium LOCA Melcor numeric coupling liquid metal blankets tritium corrosion convection turbulence WCLL blanket DCLL blanket WCLL-BB MELCOR PHTS safety analysis HCPB BB CRAFT blanket and divertor experiment plan water loop design DEMO blanket first wall ODS steel layer tungsten functionally graded coating experimental investigation EU-DEMO helium-cooled pebble bed thermal storage indirect coupled design energy balance power conversion system simulation gyrotron resonator multi-physic simulation thermal-hydraulics cooling mini-channels Raschig rings validation divertor plasma facing components thermal hydraulics SIMMER code RELAP5 code in-box LOCA WCLL breeding blanket LIFUS5/Mod3 thema EDItEUR::U Computing and Information Technology thema EDItEUR::U Computing and Information Technology::UL Operating systems Thermal-Hydraulics in Nuclear Fusion Technology: R&D and Applications |
| title | Thermal-Hydraulics in Nuclear Fusion Technology: R&D and Applications |
| title_full | Thermal-Hydraulics in Nuclear Fusion Technology: R&D and Applications |
| title_fullStr | Thermal-Hydraulics in Nuclear Fusion Technology: R&D and Applications |
| title_full_unstemmed | Thermal-Hydraulics in Nuclear Fusion Technology: R&D and Applications |
| title_short | Thermal-Hydraulics in Nuclear Fusion Technology: R&D and Applications |
| title_sort | thermal hydraulics in nuclear fusion technology r d and applications |
| topic | packing structure contact force porosity distribution tritium breeder pebble bed breeding blanket discrete element method DEMO primary heat transfer system balance of plant RELAP5 loss of flow accident once through steam generators DEMO-EU fusion reactor IFMIF-DONES facility lithium technology CFD thermo-fluid dynamics lead-lithium eutectic In-box LOCA HCLL TBS liquid metal blanket MHD benchmarking COMSOL multiphysics magneto-convection turbulent MHD large eddy simulations magnetohydrodynamics (MHD) MHD pressure drop system codes liquid metal technology WCLL BB small ESS transient Apros Magnetohydrodynamics heat transfer WCLL thermal hydraulic WLLC blanket CFETR wakes open channel flow experimental methods DONES fusion liquid lithium LOCA Melcor numeric coupling liquid metal blankets tritium corrosion convection turbulence WCLL blanket DCLL blanket WCLL-BB MELCOR PHTS safety analysis HCPB BB CRAFT blanket and divertor experiment plan water loop design DEMO blanket first wall ODS steel layer tungsten functionally graded coating experimental investigation EU-DEMO helium-cooled pebble bed thermal storage indirect coupled design energy balance power conversion system simulation gyrotron resonator multi-physic simulation thermal-hydraulics cooling mini-channels Raschig rings validation divertor plasma facing components thermal hydraulics SIMMER code RELAP5 code in-box LOCA WCLL breeding blanket LIFUS5/Mod3 thema EDItEUR::U Computing and Information Technology thema EDItEUR::U Computing and Information Technology::UL Operating systems |
| topic_facet | packing structure contact force porosity distribution tritium breeder pebble bed breeding blanket discrete element method DEMO primary heat transfer system balance of plant RELAP5 loss of flow accident once through steam generators DEMO-EU fusion reactor IFMIF-DONES facility lithium technology CFD thermo-fluid dynamics lead-lithium eutectic In-box LOCA HCLL TBS liquid metal blanket MHD benchmarking COMSOL multiphysics magneto-convection turbulent MHD large eddy simulations magnetohydrodynamics (MHD) MHD pressure drop system codes liquid metal technology WCLL BB small ESS transient Apros Magnetohydrodynamics heat transfer WCLL thermal hydraulic WLLC blanket CFETR wakes open channel flow experimental methods DONES fusion liquid lithium LOCA Melcor numeric coupling liquid metal blankets tritium corrosion convection turbulence WCLL blanket DCLL blanket WCLL-BB MELCOR PHTS safety analysis HCPB BB CRAFT blanket and divertor experiment plan water loop design DEMO blanket first wall ODS steel layer tungsten functionally graded coating experimental investigation EU-DEMO helium-cooled pebble bed thermal storage indirect coupled design energy balance power conversion system simulation gyrotron resonator multi-physic simulation thermal-hydraulics cooling mini-channels Raschig rings validation divertor plasma facing components thermal hydraulics SIMMER code RELAP5 code in-box LOCA WCLL breeding blanket LIFUS5/Mod3 thema EDItEUR::U Computing and Information Technology thema EDItEUR::U Computing and Information Technology::UL Operating systems |
| url | ONIX_20220321_9783036530321_48 |