Plasma-facing material (original) (raw)
プラズマ対向機器（プラズマたいこうきき、英: Plasma facing component, PFC）は、核融合炉の内壁を構成してプラズマに直接「対向」している機器類のこと。現在はまだ核融合炉は完成していないのでこの機器類はいずれも、開発中か開発済みで実用待ちの段階にある。
| Property | Value |
|---|---|
| dbo:abstract | In nuclear fusion power research, the plasma-facing material (or materials) (PFM) is any material used to construct the plasma-facing components (PFC), those components exposed to the plasma within which nuclear fusion occurs, and particularly the material used for the lining the first wall or divertor region of the reactor vessel. Plasma-facing materials for fusion reactor designs must support the overall steps for energy generation, these include: 1. * Generating heat through fusion, 2. * Capturing heat in the first wall, 3. * Transferring heat at a faster rate than capturing heat. 4. * Generating electricity. In addition PFMs have to operate over the lifetime of a fusion reactor vessel by handling the harsh environmental conditions, such as: 1. * Ion bombardment causing physical and chemical sputtering and therefore erosion. 2. * Ion implantation causing displacement damage and chemical composition changes 3. * High-heat fluxes (e.g. 10 MW/m) due to ELMS and other transients. 4. * Limited tritium codeposition and sequestration. 5. * Stable thermomechanical properties under operation. 6. * Limited number of negative nuclear transmutation effects Currently, fusion reactor research focuses on improving efficiency and reliability in heat generation and capture and on raising the rate of transfer. Generating electricity from heat is beyond the scope of current research, due to existing efficient heat-transfer cycles, such as heating water to operate steam turbines that drive electrical generators. Current reactor designs are fueled by deuterium-tritium (D-T) fusion reactions, which produce high-energy neutrons that can damage the first wall, however, high-energy neutrons (14.1 MeV) are needed for blanket and Tritium breeder operation. Tritium is not a naturally abundant isotope due to its short half-life, therefore for a fusion D-T reactor it will need to be bred by the nuclear reaction of lithium (Li), boron (B), or beryllium (Be) isotopes with high-energy neutrons that collide within the first wall. (en) プラズマ対向機器（プラズマたいこうきき、英: Plasma facing component, PFC）は、核融合炉の内壁を構成してプラズマに直接「対向」している機器類のこと。現在はまだ核融合炉は完成していないのでこの機器類はいずれも、開発中か開発済みで実用待ちの段階にある。 (ja) |
| dbo:thumbnail | wiki-commons:Special:FilePath/Alcator_C-Mod_Tokamak_Interior.jpg?width=300 |
| dbo:wikiPageExternalLink | http://www.ipp.mpg.de/ippcms/eng/for/projekte/pfmc/index.html http://www.ipp.mpg.de/ippcms/eng/for/veranstaltungen/konferenzen/archiv/2011/03pfmc-13/index.html |
| dbo:wikiPageID | 36952575 (xsd:integer) |
| dbo:wikiPageLength | 19128 (xsd:nonNegativeInteger) |
| dbo:wikiPageRevisionID | 1122170785 (xsd:integer) |
| dbo:wikiPageWikiLink | dbr:Beryllium dbr:Boron_carbide dbr:Joint_European_Torus dbr:Lithium dbr:Induced_radioactivity dbr:International_Fusion_Materials_Irradiation_Facility dbr:Molybdenum dbr:Erosion dbr:Nuclear_physics dbr:Fusion_power dbr:Magnetic_field dbr:Silicon_carbide dbr:Stellarator dbr:Tokamak dbr:Tokamak_Fusion_Test_Reactor dbr:Tokamak_à_configuration_variable dbr:Divertor dbr:Heat_flux dbr:ASDEX_Upgrade dbr:Alcator_C-Mod dbr:DEMOnstration_Power_Station dbc:Fusion_power dbr:Breeder_reactor dbr:Breeding_blanket dbr:Nobel_Prize_in_Physics dbr:Nuclear_fusion dbr:Graphite dbr:Tungsten dbr:Nuclear_decommissioning dbc:Materials_science dbr:TJ-II dbr:Edge-localized_mode dbr:Nuclear_transmutation dbr:Pierre-Gilles_de_Gennes dbr:Plasma_(physics) dbr:ITER dbr:National_Spherical_Torus_Experiment dbr:Neutron_flux dbr:Carbon_fibre_composite dbr:Lithium_Tokamak_Experiment dbr:Sputtering dbr:Magnetic_confinement dbr:Nuclear_power_reactor dbr:Nuclear_waste dbr:Reactor_vessel dbr:NSTX dbr:File:Alcator_C-Mod_Tokamak_Interior.jpg dbr:File:Tcv_int.jpg |
| dbp:wikiPageUsesTemplate | dbt:Cite_journal dbt:More_citations_needed dbt:Reflist dbt:Update |
| dcterms:subject | dbc:Fusion_power dbc:Materials_science |
| rdfs:comment | プラズマ対向機器（プラズマたいこうきき、英: Plasma facing component, PFC）は、核融合炉の内壁を構成してプラズマに直接「対向」している機器類のこと。現在はまだ核融合炉は完成していないのでこの機器類はいずれも、開発中か開発済みで実用待ちの段階にある。 (ja) In nuclear fusion power research, the plasma-facing material (or materials) (PFM) is any material used to construct the plasma-facing components (PFC), those components exposed to the plasma within which nuclear fusion occurs, and particularly the material used for the lining the first wall or divertor region of the reactor vessel. Plasma-facing materials for fusion reactor designs must support the overall steps for energy generation, these include: In addition PFMs have to operate over the lifetime of a fusion reactor vessel by handling the harsh environmental conditions, such as: (en) |
| rdfs:label | プラズマ対向機器 (ja) Plasma-facing material (en) |
| owl:sameAs | freebase:Plasma-facing material wikidata:Plasma-facing material dbpedia-fa:Plasma-facing material dbpedia-ja:Plasma-facing material https://global.dbpedia.org/id/4u7Vp |
| prov:wasDerivedFrom | wikipedia-en:Plasma-facing_material?oldid=1122170785&ns=0 |
| foaf:depiction | wiki-commons:Special:FilePath/Tcv_int.jpg wiki-commons:Special:FilePath/Alcator_C-Mod_Tokamak_Interior.jpg |
| foaf:isPrimaryTopicOf | wikipedia-en:Plasma-facing_material |
| is dbo:wikiPageDisambiguates of | dbr:PFM |
| is dbo:wikiPageRedirects of | dbr:Plasma-facing_components dbr:First_wall dbr:Plasma_facing_component dbr:Plasma_facing_material |
| is dbo:wikiPageWikiLink of | dbr:Hybrid_Illinois_Device_for_Research_and_Applications dbr:International_Fusion_Materials_Irradiation_Facility dbr:SST-1_(tokamak) dbr:Fusion_power dbr:General_Fusion dbr:Linus_(fusion_experiment) dbr:PFM dbr:Plasma-facing_components dbr:Tungsten dbr:First_wall dbr:TJ-II dbr:Spherical_tokamak dbr:Richard_Majeski dbr:Plasma_facing_component dbr:Plasma_facing_material |
| is foaf:primaryTopic of | wikipedia-en:Plasma-facing_material |
