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Nuclear analysis of the Single Module Segment WCLL DEMO
Fusion Engineering and Design, 2019Abstract The latest design of the Water Cooled Lithium Lead blanket for the European DEMO reactor is based on a Single Module Segment (SMS) concept for the blanket segments: the removal of the gaps between the modules (present in the former Multi Module structure design), with the consequent reduction of the neutron streaming, improves the tritium ...
Simone Noce +2 more
exaly +4 more sources
MHD pressure drop estimate for the WCLL in-magnet PbLi loop
Fusion Engineering and Design, 2020 Abstract In the Water-Cooled Lithium Lead (WCLL) blanket, the eutectic alloy lithium-lead (PbLi) is used as tritium breeder and carrier, neutron multiplier, and heat transfer medium. The PbLi hydraulic loop section in the range of the reactor field coils, which includes the blanket and a non-negligible length of the connection pipes, is affected by ...
Alessandro Tassone +2 more
exaly +2 more sources
DEMO WCLL primary heat transfer system loops activated corrosion products assessment
Fusion Engineering and Design, 2021Abstract The estimation of Activated Corrosion Products (ACPs) in fusion technology is an important input to safety assessments (e.g. occupational radiation exposure, accidental analyses). The present work aims to calculate ACPs for the First Wall (FW) and Breeder Zone (BZ) water cooling loops of the DEMO Water Cooled Lithium Lead (WCLL) fusion ...
Terranova, Nicholas, Di Pace, Luigi
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MHD flow and heat transfer in model geometries for WCLL blankets
Fusion Engineering and Design, 2017 Abstract In the water cooled lead lithium (WCLL) blanket liquid lead lithium PbLi is used as breeder, neutron multiplier, and as heat transfer medium. The released heat is removed by water that flows at a pressure of 155 bar through cooling pipes immersed in the liquid-metal pool.
Bühler, L., Mistrangelo, C.
exaly +3 more sources
The fracture mechanics behaviour of the WCLL blanket segment
Fusion Engineering and Design, 2000The fracture mechanics behaviour is a limiting factor for the lifetime of a component, especially when the reduction of toughness of the structural material because of neutron irradiation effect is taken into account. In order to investigate the end of life behaviour of the WCLL blanket segment, a fracture mechanics analysis has been performed ...
Claudio Nardi, A Palmieri
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Neutronic analyses in support of the WCLL DEMO design development
Fusion Engineering and Design, 2018Abstract In the frame of the EUROfusion Consortium programme, the Water Cooled Lithium Lead (WCLL) option has been chosen as a candidate for the breeding blanket (BB) of the European fusion power demonstration plant (DEMO) conceptual design. Neutronic analyses play a fundamental role in the development of the WCLL blanket, providing guidelines for ...
Fabio Moro +2 more
exaly +5 more sources
Preliminary RAMI analysis of WCLL blanket and breeder systems
Fusion Engineering and Design, 2015Abstract DEMO will be a prototype fusion reactor designed to prove the capability to produce electrical power in a commercially acceptable way. One of the key factors in that endeavor is the achievement of certain level of plant availability. Therefore, RAMI (Reliability, Availability, Maintainability and Inspectability) will be a key element in the ...
Jose Manuel Arroyo +4 more
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Assessment of activated corrosion products for the DEMO WCLL
Fusion Engineering and Design, 2018Abstract This paper deals with the assessment of the activated corrosion products (ACPs) for the First Wall water-cooled loop of the DEMO WCLL reactor. The aim was devoted to scan some operating parameters, not yet frozen, which eventually proved to be very important, such as the coolant temperature during plasma dwell, materials for the Steam ...
Di Pace, Luigi, Quintieri, Lina
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Integration of LiPb loops for WCLL BB of European DEMO
Fusion Engineering and Design, 2021Abstract The eutectic alloy Lithium Lead (LiPb) enriched at 90 % in 6Li is the breeder material for one of the candidate European Breeding Blanket (BB) concepts. Currently under investigation for DEMO reactor, the Water Cooled Lithium-Lead (WCLL), and for the WCLL Test Blanket Module (TBM) that will be qualified in the ITER reactor. The LiPb alloy is
Mozzillo, Rocco +4 more
openaire +2 more sources
Pb–17Li/water interaction in DEMO WCLL blanket: water micro-leaks
Fusion Engineering and Design, 2003Abstract The interaction between pressurised water and liquid Pb–17Li is a topical issue for the WCLL blanket concept and needs to be studied in detail because of the potentially significant effect on the reliability and safety of the blanket. Particularly, it seems important from the design point of view to deeply investigate the consequences of ...
I. RICAPITO +2 more
openaire +2 more sources