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Members:xxxxxHTGRCONTENTS1.Introduction2.Development3.Principle4.ConclusionsIntroduction50s-60s70s-80s90s1999Thefirstgenerationofnuclearpowerplants:feasibilityThesecondgenerationofnuclearpowerplants:Standardization,massconstructionThethirdgenerationofnuclearpowerplants：AdvancedlightwaterreactorTheforthgenerationofnuclearpowerplants：safety、lesswaste、preventionofnuclearproliferationIntroductionVery-High-TemperatureGas-CooledReactorSystem（超高温反应堆系统）Gas-CooledFastReactorSystem(气体冷却快堆系统)Lead-cooledFastReactorSystem（铅冷却快堆系统）MoltenSaltReactorSystem（熔盐反应堆系统）Sodium-CooledFastReactorSystem（钠冷却快堆系统）Supercritical-Water-CooledReactorSystem（超临界冷却反应堆系统）ApromisingoneChinaandjapanleadtheworldThefourthgenerationofnuclearenergysystem:DevelopmentFirstgenerationgascooledreactor(50s-70s)MagnoxtypegascooledreactorFuel:NaturaluraniumCoolant:CO2-400℃Moderator:GraphiteCladdingmaterial:MagnoxNoIndustrialuraniumenrichmenttechnologyNaturaluraniumHighcostLowefficiency-18.8%DevelopmentSecondgenerationgascooledreactorAdvancedgascooledreactor(AGR):Fuel:2%UO2Coolant:CO2-670℃Moderator:GraphiteCladdingmaterial:StainlesssteelLowenricheduraniumStainlesssteelSmallvolume-lowcostHighefficiency-40%DevelopmentFuel:HightemperatureceramicpelletfuelCoolant:Helium-950℃Moderator:GraphiteCladdingmaterial:CeramicsCeramicpelletfuelHeliumHighertemperatureHigherefficiencySaferbreakthroughHightemperaturegascooledreactor:PrincipleSphereceramicpelletfuelTough(不易破损)Hightemperatureresistance0.5mmfuelkernelUraniumdioxide0.92mmcoatedparticle60mmfuelspheresPrincipleCoatedparticlesaretoosmalltobeuseddirectly,sotheywillbedispersedinthegraphitemixtobepressedintothefuelentity.Then,thefuelentityisplacedinasphericalfuelelementconsistingofgraphitecladdingGraphitecladdingGraphitematrixCoatedparticlePrincipleThe60mmspherefueliscontinuouslyloadedintothecorefromthetop,andthespentfuelballwillbemeasured.Ifthespherefuelisnotuptothepredeterminedfuelconsumptiondepth,itwillbesentbacktothereactoragain.Generallythespherefuelwillbeusedmorethan10times.Spherefuel:PrincipleHeliumChemicalinertnessEasytopurifyGoodthermalconductivityPrincipleTheheliumcoolantispumpedfromthebottomofthereactorintothecore.Heliumwillbeheatedthroughthegapofspherefuel,andtheoutputtemperaturecanreach950degrees.Thenhightemperatureheliumgoesintothesteamgeneratorandmakeswatertransferintosteam.Finallyhightemperaturesteamdrivesturbinetogenerateelectricity.PrincipleInherentsafetycharacteristics：Fueltemperaturedoesnotexceed1600°ClimitunderanyaccidentconditionsFissionproductsarealwayscontainedinthefuelparticlesNoaccidentalmeltingandradioactivemassreleaseofthecoreConclusionHightemperatureandhighefficiencyHighconversionratioHighsecuritySmallenvironmentalpollution，andcanbebuiltindenselypopulatedareasBroadapplicationprospectHTGR:ConclusionChinahasindependentlydevelopedtheworld'sfirsthigh-temperaturegas-cooledreactornuclearpowerplantwiththefourthgenerationofnuclearpowertechnologyinRongchengShandongPlantoverviewShortvideoThanks!