Results 31 to 40 of about 1,034 (139)
Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket
Fusion Engineering and Design, 2018 Abstract In the frame of EUROfusion Work Package Breeding Blanket, thermal-hydraulic engineering analyses were carried out at ENEA Brasimone, in close cooperation with Sapienza University of Rome, to investigate thermal and fluid-dynamic behavior of the Water Cooled Lithium Lead Breeding Blanket, which is a candidate option for the European DEMO ...
Martelli, Emanuela +3 more
openaire +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 +11 more
doaj +1 more source
DEMO WCLL BB breeding zone cooling system design: analysis and discussion [PDF]
, 2019 The Water-Cooled Lithium-Lead (WCLL) Breeding Blanket (BB) is a key component in charge of ensuring Tritium self-sufficiency, shielding the Vacuum Vessel and removing the heat generated in the tokamak plasma.
Caruso, Gianfranco +4 more
core +1 more source
MHD mixed convection flow in the WCLL: heat transfer analysis and cooling system [PDF]
, 2019 In the Water-Cooled Lithium Lead (WCLL) blanket, a critical problem faced by the design is to ensure that the breeding zone (BZ) is properly cooled by the refrigeration system to keep the structural materials under the maximum allowed temperature by the ...
Caruso, Gianfranco +3 more
core +1 more source
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 +3 more
doaj +1 more source
On the thermal dynamic behaviour of the helium-cooled DEMO fusion reactor [PDF]
, 2019 The EU-DEMO conceptual design is being conducted among research institutions and universities from 26 countries of European Union, Switzerland and Ukraine. Its mission is to realise electricity from nuclear fusion reaction by 2050.
Barucca L. +3 more
core +1 more source
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 +3 more
doaj +1 more source
A Preliminary Exergy Analysis of the EU DEMO Fusion Reactor [PDF]
, 2019 Purpose of the present study is the exergy analysis of EU DEMO pulsed fusion power plant considering the Primary Heat Transfer Systems, the Intermediate Heat Transfer System (IHTS) including the Energy Storage System (ESS) as a first option to ensure the
Caruso, Gianfranco +2 more
core +1 more source
Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM Code [PDF]
, 2023 This work presents the results of the implementation in the GEneral Tokamak THErmal-hydraulic Model of available models for the generation and transport of any dispersed material in flowing PbLi eutectic mixture.
Arena, Pietro +6 more
core +2 more sources
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 +3 more
doaj +1 more source