Results 161 to 170 of about 513 (179)

The fracture mechanics behaviour of the WCLL blanket segment

Fusion Engineering and Design, 2000
The 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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Preliminary RAMI analysis of WCLL blanket and breeder systems

Fusion Engineering and Design, 2015
Abstract 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, Richard Brown, Jon Harman, Elena Rosa, Angel Ibarra   +4 more
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Assessment of activated corrosion products for the DEMO WCLL

Fusion Engineering and Design, 2018
Abstract 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, 2021
Abstract 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, Utili, Marco, Venturini, Alessandro, Tincani, Amelia, Gliss, Curt   +4 more
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Nuclear analysis of the Single Module Segment WCLL DEMO

Fusion Engineering and Design, 2019
Abstract 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, Fabio Moro, Francesco Romanelli, Rosaria Villari   +3 more
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Pb–17Li/water interaction in DEMO WCLL blanket: water micro-leaks

Fusion Engineering and Design, 2003
Abstract 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, CIAMPICHETTI, ANDREA, G. BENAMATI   +2 more
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WCLL Blanket Module Structure Variation Influence on Neutron Activation Inventories

IEEE Transactions on Plasma Science, 2019
One of the conceptual designs of the breeder blanket for a European demonstration fusion power station (DEMO) is the water-cooled lithium lead (WCLL) concept. The design development of the WCLL blanket in recent years has undergone the evolution of the neutronics model employing the MCNP code, with key changes in radial lengths and thickness as well as
Andrius Tidikas, Gediminas Stankunas
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An overview on tritium permeation barrier development for WCLL blanket concept

Journal of Nuclear Materials, 2004
The reduction of tritium permeation through blanket structural materials and cooling tubes has to be carefully evaluated to minimise radiological hazards. A strong effort has been made in the past to select the best technological solution for the realisation of tritium permeation barriers (TPB) on complex structures not directly accessible after the
CIAMPICHETTI, ANDREA, AIELLO ANTONIO, BENAMATI GIANLUCA   +2 more
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Rationale and method for design of DEMO WCLL breeding blanket poloidal segmentation

Fusion Engineering and Design, 2017
Abstract One of the most critical components in the design of DEMO Power Plant is the Breeding Blanket. Currently, four candidates are investigated as options for DEMO. One of these is the Water Coolant Lithium Lead Breeding Blanket. A new concept design has been proposed and investigated in 2015.
Rocco Mozzillo, Alessandro Del Nevo, Emanuela Martelli, Giuseppe Di Gironimo   +3 more
openaire   +4 more sources

Maintenance study on WCLL-TBS ancillary systems in process room

Fusion Engineering and Design
The Water-Cooled Lithium Lead Test Blanket System (WCLL-TBS) is one of the European TBS candidates for being installed and operated in ITER. The ongoing activities toward the Preliminary Design Review of the WCLL-TBS Ancillary Systems include the reallocation of their units in the reserved space, also in the view of the proper execution of the ...
Bonavolontà, Ugo, Ferrer, Carlos Ortiz, La Rovere, Stefano, Marzullo, Domenico   +3 more
openaire   +2 more sources