Results 51 to 60 of about 502,482 (107)

Model Development and Transient Analysis of the WCLL BB BOP DEMO Configuration Using the Apros System Code

Energies, 2021
Extensive modelling and analytical work has been carried out considering the water-cooled lithium–lead breeding blanket (WCLL BB) balance of plant (BOP) configuration of the demonstration power plant (DEMO) using the Apros system code, developed by VTT ...
Marton Szogradi, Sixten Norrman
doaj   +1 more source

A complete EM analysis of DEMO WCLL Breeding Blanket segments during VDE-up

Fusion Engineering and Design, 2018
Abstract Considerable effort is made within the EUROfusion consortium to analyse the electromagnetic (EM) loads that act on the in-vessel components of DEMO during normal and off-normal operations. These loads are important, often design driving, inputs for the structural assessment of such components. With regard to the Breeding Blanket (BB) project,
Ivan Alessio Maione, Massimo Roccella, Anna Marin, Claudio Bertolini, Flavio Lucca   +4 more
openalex   +5 more sources

Advancements in Designing the DEMO Driver Blanket System at the EU DEMO Pre-Conceptual Design Phase: Overview, Challenges and Opportunities

Journal of Nuclear Engineering, 2023
The EU conducted the pre-conceptual design (PCD) phase of the demonstration reactor (DEMO) during 2014–2020 under the framework of the EUROfusion consortium.
Francisco A. Hernández, Pietro Arena, Lorenzo V. Boccaccini, Ion Cristescu, Alessandro Del Nevo, Pierre Sardain, Gandolfo A. Spagnuolo, Marco Utili, Alessandro Venturini, Guangming Zhou   +9 more
doaj   +1 more source

Conceptual Design of the Steam Generators for the EU DEMO WCLL Reactor

Energies, 2023
In the framework of the EUROfusion Horizon Europe Programme, ENEA and its linked third parties are in charge of the conceptual design of the steam generators belonging to EU DEMO WCLL Breeding Blanket Primary Heat Transfer Systems (BB PHTSs).
Amelia Tincani, Cristiano Ciurluini, Alessandro Del Nevo, Fabio Giannetti, Andrea Tarallo, Claudio Tripodo, Antonio Cammi, Alessandra Vannoni, Marica Eboli, Tommaso Del Moro, Pierdomenico Lorusso, Luciana Barucca   +11 more
doaj   +1 more source

Predictive Modelling of Tritium Breeding Ratio (Tbr) in EU Demo Wcll Blankets: Openmc Simulations and Analytical Insights

Fusion Engineering and Design
Dahmane Mazed, Noureddine Rebiai, Maxime Chiletti, Frédéric Gérardin   +3 more
  +4 more sources

3D MHD analysis of prototypical manifold for liquid metal blankets

Nuclear Fusion, 2023
The water-cooled lead lithium (WCLL) and the dual-cooled lead lithium (DCLL) are two of the breeding blanket (BB) concepts that the EUROfusion consortium is pursuing in the framework of the development of the fusion reactor industrial demonstrator DEMO ...
Simone Siriano, Fernando Roca Urgorri, Alessandro Tassone, Gianfranco Caruso   +3 more
doaj   +1 more source

Preliminary estimates of tritium permeation and retention in the first wall of DEMO due to ion bombardment

Nuclear Materials and Energy, 2021
Tritium self-sufficiency presents a critical engineering challenge for DEMO, requiring efficient breeding and extraction systems, as well as minimizing tritium losses to the surrounding systems, such as plasma-facing components, vacuum vessel, cooling ...
R. Arredondo, K. Schmid, F. Subba, G.A. Spagnuolo   +3 more
doaj   +1 more source

Mechanical properties of several newly produced RAFM steels with Tungsten content in the range of 2 wt%

Nuclear Materials and Energy, 2020
The contribution of ENEA together with Rina-CSM to the Eurofusion programme “WPMAT-Advanced Seels” deals with the development of innovative RAFM steels able to withstand the critical temperatures typical of the different operational environments foreseen
C. Cristalli, L. Pilloni, O. Tassa, L. Bozzetto   +3 more
doaj   +1 more source

Preliminary assessment of tritium permeation and retention in the European Water Cooled Lithium Lead Test Blanket Module with TESSIM-X

Nuclear Materials and Energy, 2022
Tritium self-sufficiency is a key requirement for future fusion power plants. Therefore, it will be necessary to minimize tritium losses to the surrounding systems, such as the tritium breeding modules, plasma-facing components, cooling system, etc ...
R. Arredondo, K. Schmid, I. Ricapito, A. Lukenskas, G.A. Spagnuolo   +4 more
doaj   +1 more source

Embrittlement of WCLL blanket and its fracture mechanical assessment

Nuclear Fusion, 2023
In the European fusion programme, the Water Cooled Lithium Lead breeding blanket (WCLL BB) uses EUROFER as a structural material cooled with water at temperatures between 295 °C–328 °C and a pressure of 155 bar.
Jarir Aktaa, Ermile Gaganidze, Gaetano Bongioví, Pietro Arena, Gandolfo Alessandro Spagnuolo, Giacomo Aiello, Pierluigi Chiovaro, Christian Bachmann   +7 more
doaj   +1 more source