0000000000136168

AUTHOR

A. Morin

showing 4 related works from this author

Thermo-mechanical analyses and ways of optimization of the helium cooled DEMO First Wall under RCC-MRx rules

2017

Abstract The EUROfusion Consortium develops a design of a fusion power demonstrator plant (DEMO) in the framework of the European “Horizon 2020” innovation and research program. One of the key components in the fusion reactor is the Breeding Blanket (BB) surrounding the plasma, ensuring tritium self-sufficiency, heat removal for conversion into electricity, and neutron shielding. Among the 4 candidates for the DEMO BB, 2 of them use helium as coolant (HCPB, HCLL), and another one (DCLL) uses helium to cool down the First Wall (FW) only. Due to uncertainties regarding the plasma Heat Flux (HF) load the DEMO BB integrated FW will have to cope with, a set of sensitive thermal and stress analys…

Materials scienceRCC-MRxNuclear engineeringchemistry.chemical_elementBlanket01 natural sciences7. Clean energy010305 fluids & plasmasStress (mechanics)[SPI]Engineering Sciences [physics]Materials Science(all)0103 physical sciencesGeneral Materials ScienceCast3M010306 general physicsDEMOHeliumSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringSteady stateBreeding BlanketMechanical EngineeringThermo-mechanicFusion powerCoolantFirst WallchemistryCreepHeat fluxNuclear Energy and EngineeringHCLLDEMO; Breeding; Blanket; HCLL; RCC-MRx; Thermo-mechanics; Cast3M; First WallMaterials Science (all)
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Thermal optimization of the Helium-Cooled Lithium Lead breeding zone layout design regarding TBR enhancement

2017

Abstract Within the framework of EUROfusion R&D activities, CEA-Saclay has carried out an investigation of the thermal and mechanical performances of alternative designs intended to enhance the Tritium Breeding Ratio (TBR) of the Helium-Cooled Lithium Lead (HCLL) Breeding Blanket (BB) for DEMO. Neutronic calculations performed on the 2014 DEMO HCLL baseline predicted a value of TBR equal to 1.07, lower than the required value of 1.1, necessary to ensure the tritium self-sufficiency of the breeding blanket taking into account uncertainties. In order to reach the TBR target, the strategy of the steel amount reduction inside the HCLL module breeding zone (BZ) has been followed by suppressing s…

Materials scienceNuclear engineeringFinite elementschemistry.chemical_elementDEMO HCLL Breeding blanket Thermo-mechanics Finite elements Cast3MBlanketcomputer.software_genre01 natural sciences7. Clean energy010305 fluids & plasmas[SPI]Engineering Sciences [physics]Materials Science(all)0103 physical sciencesThermalGeneral Materials ScienceCast3M010306 general physicsDEMOHeliumSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringThermo-mechanicsPage layoutMechanical EngineeringFinite element methodStiffeningchemistryNuclear Energy and EngineeringHCLLBreeding blanketReduction (mathematics)Loss-of-coolant accidentcomputerFusion Engineering and Design
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Status of the EU DEMO HCLL breeding blanket design development

2018

International audience; In the framework of the European “HORIZON 2020” innovation and research programme, the EUROfusion Consortium develops a design of a fusion power demonstrator (DEMO). One of the key components in the fusion reactor is the Breeding Blanket (BB) surrounding the plasma, ensuring tritium self-sufficiency, heat removal for conversion into electricity, and neutron shielding. CEA-Saclay, with the support of Wigner-RCP and Centrum výzkumu Řež, is in charge of the development of one of the four BB concepts investigated in Europe for DEMO: the Helium Cooled Lithium Lead (HCLL) BB. The rationales of the HCLL are the use of Eurofer as structural material, eutectic liquid lithium-…

Computer scienceNuclear engineeringBlanketBreeding7. Clean energy01 natural sciences010305 fluids & plasmasTritium breeding ratio0103 physical sciencesGeneral Materials Science010306 general physicsDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringBreeding BlanketHelium gasMechanical EngineeringFusion power[INFO.INFO-MO]Computer Science [cs]/Modeling and SimulationCoolantNuclear Energy and EngineeringElectromagnetic shieldingHCLLBlanketMaterials Science (all)Design evolution
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Optimization of the first wall for the DEMO water cooled lithium lead blanket

2015

The maximum heat load capacity of a DEMO First Wall (FW) of reasonable cost may impact the decision of the implementation of limiters in DEMO. An estimate of the engineering limit of the FW heat load capacity is an essential input for this decision. This paper describes the work performed to optimize the FW of the Water Cooled Lithium-Lead (WCLL) blanket concept for DEMO fusion reactor in order to increase its maximum heat load capacity. The optimization is based on the use of water at typical Pressurised Water Reactors conditions as coolant. The present WCLL FW with a waved plasma-faced surface and with circular channels was studied and the heat load limit has been predicted with FEM analy…

Work (thermodynamics)DesignMaterials scienceMechanical EngineeringNuclear engineeringDesign;DEMO;Blanket;WCLL;First WallFusion powerBlanketFinite element methodWCLLCoolantDesign for manufacturability[SPI]Engineering Sciences [physics]First WallDEMO Blanket WCLL Design First WallNuclear Energy and EngineeringThermalLimiterBlanketGeneral Materials ScienceDEMOSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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