6533b81ffe1ef96bd1277d83
RESEARCH PRODUCT
Overview of the HCPB Research Activities in EUROfusion
Ion CristescuGabor NadasiM. MoscardiniSebastian RuckPavel PereslavtsevT. HernándezHeiko NeubergerXue Z. JinP. KurinskiyBradut E. GhidersaRegina KnitterGuangming ZhouLorenzo V. BoccacciniIvan Alessio MaioneV. ChakinBela KissR. RolliEvaldas BubelisMaría Asenjo GonzálezFrancisco A. HernándezOliver LeysGandolfo Alessandro SpagnuoloWolfgang HeringChristian ZeileFrederik ArbeiterM.h.h. KolbMarc KamlahPavel VladimirovS. Pupeschisubject
Nuclear and High Energy PhysicsPower stationHelium-cooled pebble bed (HCPB)BlanketCondensed Matter Physics7. Clean energy01 natural sciences010305 fluids & plasmas13. Climate action0103 physical sciencesdemonstration fusion reactor (DEMO)Systems engineeringEUROfusion010306 general physicsDesign evolutiontritium breedingSettore ING-IND/19 - Impianti Nuclearidescription
In the framework of the EUROfusion’s Power Plant Physics and Technology, the working package breeding blanket (BB) aims at investigating four different BB concepts for an EU demonstration fusion reactor (DEMO). One of these concepts is the helium-cooled pebble bed (HCPB) BB, which is based on the use of pebble beds of lithiated ternary compounds and Be or beryllides as tritium breeder and multiplier materials, respectively, EUROFER97 as structural steel and He as coolant. This paper aims at giving an overview of the EU HCPB BB Research and Development (R&D) being developed at KIT, in collaboration with Wigner-RCP, BUTE-INT, and CIEMAT. The paper gives an outline of the HCPB BB design evolution, state-of-the-art basic functionalities, requirements and performances, and the associated R&D activities in the areas of design, functional materials, manufacturing, and testing. In addition, attention is given also to the activities dedicated to the development of heat transfer augmentation techniques for the first wall and the corresponding testing. Due to their nature as design drivers, a brief overview in the R&D of key HCPB interfacing areas is given as well, namely, the tritium extraction and recovery system, the primary heat transfer and power conversion systems, and safety topics, as well as some specific activities regarding the integration of in-vessel systems through the BB. As concluding remarks, an outline of the standing challenges and future R&D plans is summarized.
year | journal | country | edition | language |
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2018-06-01 |