简介：TheChineseFusionEngineeringTokamakReactor(CFETR)isanimportantintermediatedevicebetweenITERandDEMO.TheWaterCooledCeramicBreeder(WCCB)blanketwhosestructuralmaterialismainlymadeofReducedActivationFerritic/Martensitic(RAFM)steel,isoneofthecandidateconceptualblanketdesign.AnanalysisofrippleanderrorfieldinducedbyRAFMsteelinWCCBisevaluatedwiththemethodofstaticmagneticanalysisintheANSYScode.Significantadditionalmagneticfieldisproducedbyblanketanditleadstoanincreasedripplefield.Maximumripplealongtheseparatrixlinereaches0.53%whichishigherthan0.5%oftheacceptabledesignvalue.Simultaneously,oneblanketmoduleistakenoutforheatingpurposeandtheresultingerrorfieldiscalculatedtobeseriouslyagainsttherequirement.

简介：Thewatercooledceramicbreeder(WCCB)blanketemployingpressurizedwaterasacoolantisoneofthebreedingblanketcandidatesfortheChinaFusionEngineeringTestReactor(CFETR).Someupdatingofneutronicsanalyseswasneeded,becausetherewerechangesintheneutronicsperformanceoftheblanketasseveralsignificantmodificationsandimprovementshavebeenadoptedfortheWCCBblanket,includingtheoptimizationofradialbuild-upandcustomizedstructureforeachblanketmodule.A22.5degreetoroidalsymmetricaltorussector3DneutronicsmodelcontainingtheupdateddesignoftheWCCBblanketmoduleswasdevelopedfortheneutronicsanalyses.Thetritiumbreedingcapability,nuclearheatingpower,radiationdamage,anddecayheatwerecalculatedbytheMCNPandFISPACTcode.Theresultsshowthatthepackingfactorand~6Lienrichmentofthebreedershouldbothbenolessthan0.8toensuretritiumself-sufficiency.Thenuclearheatingpoweroftheblanketunder200MWfusionpowerreaches201.23MW.Thedisplacementperatomperfullpoweryear(FPY)oftheplasma-facingcomponentandfirstwallreach0.90and2.60,respectively.ThepeakHproductionratereaches150.79appm/FPYandthepeakHeproductionreaches29.09appm/FPYinblanketmodule#3.Thetotaldecayheatoftheblanketmodulesis2.64MWat1saftershutdownandtheaveragedecayheatdensitycanreach11.09kWm~(-3)atthattime.Thedecayheatdensityoftheblanketmodulesslowlydecreasestolowerthan10Wm~(-3)inmorethantenyears.

简介：Inordertoinvestigatethenuclearresponsetothewater-cooledceramicbreederblanketmodelsforCFETR,adetailed3Dneutronicsmodelwith22.5otorussectorwasdevelopedbasedontheintegratedgeometryofCFETR,includingheterogeneousWCCBblanketmodels,shield,divertor,vacuumvessel,toroidalandpoloidalmagnets,andports.UsingtheMonteCarloN-ParticleTransportCodeMCNP5andIAEAFusionEvaluatedNuclearDataLibraryFENDL2.1,theneutronicsanalyseswereperformed.Theneutronwallloading,tritiumbreedingratio,thenuclearheating,neutron-inducedatomicdisplacementdamage,andgasproductionweredetermined.TheresultsindicatethattheglobalTBRofnolessthan1.2willbeabigchallengeforthewatercooledceramicbreederblanketforCFETR.

简介：摘要：随着全球能源需求的日益增长，聚变能源作为清洁、可再生的能源形式，受到了广泛关注。中国聚变工程试验堆（CFETR）作为实现聚变能源的重要装置，其稳定运行对实现聚变能源的商业化应用具有重要意义。在CFETR中，馈线导体作为传输聚变反应产生能量的关键部件，其设计与热稳定性直接关系到整个装置的性能和安全性。基于此，本篇文章对CFETR馈线导体设计与热稳定性进行研究，以供参考。

简介：为了研究奥氏体钢作为中国聚变工程实验堆第一壁候选结构材料时的蠕变寿命,利用有限元方法和Larson-Miller蠕变寿命外推模型,结合奥氏体钢的辐照后蠕变断裂实验数据,探讨了热流密度、壁厚和冷却剂入口温度等参数对蠕变寿命的影响,分析比较了AISI316、冷加工AISI316及含Ti冷加工15-15Ti的辐照后蠕变性能。结果表明：奥氏体钢的辐照后蠕变寿命随热流密度、壁厚和冷却剂入口温度的增大而减小;冷加工处理并没有提升奥氏体钢的辐照后蠕变寿命,而含Ti冷加工15-15Ti具有较优异的辐照后蠕变性能。