0000000000628116

AUTHOR

J. Szczepanski

showing 3 related works from this author

Further improvements of the water-cooled Pb–17Li blanket

2001

Abstract The water-cooled lithium–lead (WCLL) blanket is based on reduced-activation ferritic–martensitic steel as the structural material, the liquid alloy Pb–17Li as breeder and neutron multiplier, and water at typical PWR conditions as coolant. It was developed for DEMO specifications and shall be tested in ITER. In 1999, a reactor parameter optimization was performed in the EU which yielded improved specifications of what could be an attractive fusion power plant. Compared to DEMO, such a power reactor would be different in lay-out, size and performance, thus requiring to better exploit the potential of the WCLL blanket concept in conjunction with a water-cooled divertor. Several new ap…

Computer scienceMechanical EngineeringDivertorReference designWater cooledNuclear engineeringPower reactorFusion powerLiquid alloyBlanketCoolantNuclear physicsNuclear Energy and EngineeringGeneral Materials ScienceCivil and Structural EngineeringFusion Engineering and Design
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On the use of tin–lithium alloys as breeder material for blankets of fusion power plants

2000

Abstract Tin–lithium alloys have several attractive thermo-physical properties, in particular high thermal conductivity and heat capacity, that make them potentially interesting candidates for use in liquid metal blankets. This paper presents an evaluation of the advantages and drawbacks caused by the substitution of the currently employed alloy lead–lithium (Pb–17Li) by a suitable tin–lithium alloy: (i) for the European water-cooled Pb–17Li (WCLL) blanket concept with reduced activation ferritic–martensitic steel as the structural material; (ii) for the European self-cooled TAURO blanket with SiCf/SiC as the structural material. It was found that in none of these blankets Sn–Li alloys woul…

Nuclear and High Energy PhysicsLiquid metalMaterials scienceAlloyMetallurgychemistry.chemical_elementBlanketengineering.materialFusion powerBreeder (animal)Thermal conductivityNuclear Energy and EngineeringchemistryengineeringGeneral Materials ScienceLithiumTinNuclear chemistryJournal of Nuclear Materials
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Potential and limits of water-cooled Pb–17Li blankets and divertors for a fusion power plant

2000

Abstract Blankets and divertors are key components of a fusion power plant. They have a large impact on the overall plant design, its performance and availability, and on the cost of electricity. The water-cooled Pb–17Li (WCLL) blanket uses reduced activation ferritic–martensitic steel as structural material. It was previously validated under numerous aspects such as TBR, mechanical and thermo-mechanical stability, thermal–hydraulics, MHD, safety and others. This was done assuming the specifications for a European DEMOnstration reactor which were fixed back in 1989. A WCLL blanket would best be combined with a water-cooled divertor so that a single coolant could be used for the entire react…

Mechanical EngineeringNuclear engineeringDivertorFusion powerBlanketNuclear reactorCoolantlaw.inventionNuclear Energy and EngineeringlawWater coolingEnvironmental scienceGeneral Materials ScienceCost of electricity by sourceCivil and Structural EngineeringPower densityFusion Engineering and Design
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