Search results for "CPB"

showing 4 items of 24 documents

Maturation of critical technologies for the DEMO balance of plant systems

2022

The Pre-Concept Design (PCD) of the Balance of Plant (BoP) systems of the EU-DEMO power plant is described in this paper for both breeding blanket (BB) concepts under assessment, namely the Water Cooled Lithium Lead (WCLL) BB and the Helium Cooled Pebble Bed (HCPB) BB. Moreover, the results of a preliminary evaluation of a number of BoP variants are discussed. This paper outlines the steps of the BoP design development, highlighting the project objectives and the strategy for their achievement under the very challenging requirements which include, among others, the intermittent nature of the DEMO plasma heat source. The main achievements during the PCD Phase will be reported together with t…

TechnologyBalance of plantElectric power distributionMechanical EngineeringHCPB BBSteam generatorPower conversion systemPower plants -- Design and constructionNuclear Energy and EngineeringSteam-boilersGeneral Materials SciencePower-plants -- Europebalance of plant; DEMO; HCPB BB; power conversion system; steam generator; WCLL BBddc:600DEMOWCLL BBSettore ING-IND/19 - Impianti NucleariDEMO; Balance of plant; WCLL BB; HCPB BB; Steam generator; Power conversion systemCivil and Structural Engineering
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Preliminary thermal-hydraulic analysis of the EU-DEMO Helium-Cooled Pebble Bed fusion reactor by using the RELAP5-3D system code

2021

Abstract In the frame of the activities promoted and encouraged by the EUROfusion Consortium aimed at developing the EU-DEMO fusion reactor, great emphasis has been placed at a very early stage of the design to incorporate the provisions needed to improve the overall plant safety and reliability performances as well as to analyse possible mitigation actions. In this framework, the research activity has been focused on the representative and safety relevant cooling loop of the Helium Cooled Pebble Bed (HCPB) Breeding Blanket (BB) Primary Heat Transfer System (PHTS), purposely selected by the safety team, in order to assess its thermal-hydraulic behaviour during normal operational conditions …

TechnologyComputer science020209 energyNuclear engineeringHCPBchemistry.chemical_element02 engineering and technologyBlanket7. Clean energy01 natural sciences010305 fluids & plasmasThermal hydraulicsReliability (semiconductor)0103 physical sciences0202 electrical engineering electronic engineering information engineeringGeneral Materials ScienceRELAP5-3DSafety and EnvironmentHeliumSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringSteady stateFinite volume methodMechanical EngineeringFusion powerEU-DEMONuclear Energy and EngineeringchemistryThermal-hydraulicsHeat transferddc:600
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Validation of Multi-Physics Integrated Procedure for the HCPB Breeding Blanket

2019

The wide range of requirements and constraints involved in the design of nuclear components for fusion reactors makes the development of multi-physics analysis procedures of utmost importance. In the framework of the European DEMO project, the Karlsruhe Institute of Technology (KIT) is dedicating several efforts to the development of a multi-physics analysis tool allowing the characterization of breeding blanket design points which are consistent from the neutronic, thermal-hydraulic and thermal-mechanical points of view. In particular, a procedure developed at KIT is characterized by the implementation of analysis software only. A preliminary step for the validation of such a procedure ha…

Technologybreeding blanketHCPBDEMO reactorBlanketFusion power7. Clean energy01 natural sciences010305 fluids & plasmasComputational Mathematics0103 physical sciencesComputer Science (miscellaneous)Systems engineeringdesign pointmulti-physicscoupling010306 general physicsddc:600Settore ING-IND/19 - Impianti Nucleari
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Experimental tests on Li-ceramic breeders for the helium cooled pebble bed (HCPB) blanket design

2003

The Helium Cooled Pebble Bed (HCPB) Test Blanket Module (TBM) to be tested in ITER (International Thermonuclear Experimental Reactor) Reactor foresees the utilization of Lithiate ceramics as Tritium breeder in form of pebble beds. Since 1998, ENEA has launched many experimental activities for the evaluation of the breeder thermomechanics and the interaction between the pebble beds and the prismatic steel containment walls. Main objectives of these activities are the measurement of the pebble bed effective thermal conductivity, the wall heat transfer coefficient, the pressure loads and deformations on the lateral walls and their dependency from the mechanical constraints. The paper presents …

Thermonuclear fusionMaterials scienceTokamakHCPBMechanical EngineeringNuclear engineeringHeat transfer coefficientBlanketFusion powerlaw.inventionNuclear physicsBreeder (animal)Li-ceramic breederNuclear Energy and EngineeringlawExperimental testHeat transferGeneral Materials SciencePebbleSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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