Results 41 to 50 of about 3,402 (266)

The Impact of Energy Renovation on Continuously and Intermittently Heated Residential Buildings in Southern Europe

open access: yesBuildings, 2022
To achieve carbon neutrality in the EU, it is important to renovate the existing EU residential buildings for a higher building energy efficiency.
Yangmin Wang   +4 more
doaj   +1 more source

Parametric thermal analysis for the optimization of Double Walled Tubes layout in the Water Cooled Lithium Lead inboard blanket of DEMO fusion reactor [PDF]

open access: yes, 2019
Within the roadmap that will lead to the nuclear fusion exploitation for electric energy generation, the construction of a DEMOnstration (DEMO) reactor is, probably, the most important milestone to be reached since it will demonstrate the technological ...
Arena P.   +4 more
core   +1 more source

DEMO WCLL BB breeding zone cooling system design: analysis and discussion [PDF]

open access: yes, 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

Preliminary evaluation of the expansion system size for a pressurized gas loop: Application to a fusion reactor based on a helium-cooled blanket [PDF]

open access: yes, 2017
Some considerations to preliminarily design the size of the Expansion Volume (EV) and the relief pipes for a Vacuum Vessel Pressure Suppression System, to be adopted in a fusion reactor based on a helium cooled blanket, are presented.
CARUSO, Gianfranco, NOBILI, MATTEO
core   +1 more source

The EUROfusion materials property handbook for DEMO in-vessel components—Status and the challenge to improve confidence level for engineering data [PDF]

open access: yes, 2020
The development of a specific materials database and handbook, for engineering design of in-vessel components of EU-DEMO, is an essential requirement for assessing the structural integrity by design. For baseline in-vessel materials, including EURFOER97,
Diegele, E.   +6 more
core   +2 more sources

Thermomechanical Analysis of a PFC Integrating W Lattice Armour in Response to Different Plasma Scenarios Predicted in the EU-DEMO Tokamak

open access: yesJournal of Nuclear Engineering, 2022
Despite the high performance exhibited by tungsten (W), no material would be able to withstand the huge loads expected with extreme plasma transients in EU-DEMO and future reactors, where the installation of sacrificial first wall limiters is essential ...
Damiano Paoletti   +9 more
doaj   +1 more source

MHD mixed convection flow in the WCLL: heat transfer analysis and cooling system [PDF]

open access: yes, 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

EU DEMO EC system preliminary conceptual design

open access: yesFusion Engineering and Design, 2018
The engineering design and R&D of auxiliary heating systems and their sub-systems are a key activities in the frame of the present conceptual design phase for a first of a kind DEMOnstration Fusion Power Plant in order to develop a system capable of achieving and controlling burning plasmas.
Garavaglia S   +29 more
openaire   +4 more sources

Study of the Effective Torus Exhaust High Vacuum Pumping System Performance in the Inner Tritium Plant Loop of EU-DEMO [PDF]

open access: yes, 2023
The requirement for a reduction of the tritium inventory of the European demonstration fusion reactor (EU-DEMO) has led to the active research and development of a continuously working pumping process termed “KALPUREX.” This process foresees the direct ...
Day, Christian   +3 more
core   +2 more sources

Modelling an in-vessel loss of coolant accident in the EU DEMO WCLL breeding blanket with the GETTHEM code [PDF]

open access: yes, 2018
One of the accidents to be analyzed for the operation of the EU DEMO tokamak reactor is the in-vessel Loss-Of-Coolant Accident (LOCA), in which a postulated rupture in the First Wall causes a rapid pressurization of the Vacuum Vessel (VV).
Bertinetti, Andrea   +5 more
core   +1 more source

Home - About - Disclaimer - Privacy