Hernández, Francisco A.

Lu, Yudong

Zhou, Guangming

English

KITopen

Water cooled Lead Ceramic Breeder blanketfor fusion power plantsKarlsruhe Institute of Technology (KIT)Karlsruhe, Germany*Email/Skype: guangming.zhou@hotmail.comGuangming Zhou*, Yudong Lu, Francisco A. Hernández#109Introduction Recently, research activities on an innovative alternative blanket concept (a Water cooled Lead Ceramic Breeder), in which Lead /Lead-alloy is used as neutron multiplier, ceramic pebbles as tritium breeder, pressurized water as coolant, are on-going. This concept avoids the potential safety issue (Be-Water reaction in case of water leakage) when Beryllium is used as neutronmultiplier in a water cooled blanket concept. After many iterations of nuclear, thermal hydraulic and thermal mechanical analysis, a sound configuration was selected.Neutronics AnalysisSummaryThis work has been carried out within the framework of theEUROfusion Consortium and has received funding from theEuratom research and training programme 2014-2018 and2019-2020 under grant agreement No 633053. The views andopinions expressed herein do not necessarily reflect those ofthe European Commission. The authors also acknowledge thesupport by the state of Baden-Wuerttemberg through bwHPC.KIT – The Research University in the Helmholtz Associationwww.kit.edu A water cooled lead ceramic breeder blanket was proposed to overcome the challenges, facing water-cooled blanket concept utilizing Beryllium. Nuclear, thermal-hydraulic and thermomechanical analysis iterations were performed, leading to a sound design with TBR 1.17 (temp. and stresslevel OK).Design FeaturesCoolant: 15.5 MPa water with Tinlet/Toutlet =295/325 °C Structural material: EUROFERNeutron multiplier: Lead / Lead-alloyTritium breeder: Lithium Ceramic PebblesThicksidewallFirst wallBack supportingstructureTemp. All [°C] Stress [MPa]AA-AB-BBNeutronic modelOutboard sliceWaterLi-ceramicsLead/lead-alloyEuroferHomogenous modelTemp. Eurofer [°C]Thermal and Thermo-mechanical AnalysisAfter several design iterations, temperature on materials are OK, stress level is acceptable.After several design iterations with thermal, and thermomechanical analysis, a configuration with TBR of 1.17 is selected.  31st Symposium on Fusion Technology (SOFT2020)20th – 25th September 2020, Virtual Edition

Water cooled Lead Ceramic Breeder blanket for fusion power plants

https://publikationen.bibliothek.kit.edu/1000124856/90220570

Water cooled Lead Ceramic Breeder blanket for fusion power plants

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