Results 61 to 70 of about 119 (88)

Dose rate evaluation in the technical premises of the demo fusion reactor using the serpent Monte Carlo code [PDF]

Nuclear Technology and Radiation Protection
This paper presents a dose rate assessment within the DEMO fusion reactor's auxiliary premises, focusing on activated water and Activated Corrosion Products as primary radiation sources.
Sereda Svitlana, Sereda Serhii, Ciattaglia Sergio, Nosovsky Anatoly, Gulik Volodymyr   +4 more
doaj   +1 more source

On the impact of the heat transfer modelling approach on the prediction of EU-DEMO WCLL breeding blanket thermal performances

Fusion Engineering and Design, 2020
Caruso G, Alessandro Del Nevo, Pietro Alessandro Di Maio   +2 more
exaly   +2 more sources

Hybrid 1D + 2D Modelling for the Assessment of the Heat Transfer in the EU DEMO Water-Cooled Lithium-Lead Manifolds

Energies, 2020
The European demonstration fusion power reactor (EU DEMO) tokamak will be the first European fusion device to produce electricity and to include a breeding blanket (BB).
Antonio Froio, Andrea Bertinetti, Alessandro Del Nevo, Laura Savoldi   +3 more
doaj   +1 more source

W-HYDRA: a new experimental platform for the Water-Cooled Lead Lithium Breeding Blanket

Nuclear Fusion
In the framework of the activities coordinated by the EUROfusion consortium, the Water thermal-HYDRAulic (W-HYDRA) experimental platform is being built at the ENEA Brasimone Research Centre in order to support the development of the Water-Cooled Lead ...
P. Arena, A. Del Nevo, M. Eboli, B. Gonfiotti, P. Maccari, R. Marinari, A. Tincani, N. Badodi, G. Bongiovì, I. Catanzaro, F. Galleni, C. Risi, L.L. Sanasi, A. Tarallo, A. Vannoni   +14 more
doaj   +1 more source

Tritium transport model at breeder unit level for HCLL breeding blanket

Fusion Engineering and Design, 2019
Abstract The Helium-Cooled Lithium Lead (HCLL) breeding blanket is one of the European blanket designs proposed for DEMO reactor. A tritium transport model is fundamental for the correct assessment of both design and safety, in order to guarantee tritium self-sufficiency and to characterize tritium concentrations, inventories and losses.
Raffaella Testoni, Luigi Candido, Marco Utili, Massimo Zucchetti   +3 more
openaire   +3 more sources

Tritium transport model at the minimal functional unit level for HCLL and WCLL breeding blankets of DEMO

Fusion Engineering and Design, 2018
Abstract The Helium-Cooled Lithium-Lead (HCLL) and Water-Cooled Lithium-Lead (WCLL) Breeding Blankets are two of the four European blanket designs proposed for the DEMO reactor. A tritium transport model inside the blanket is fundamental to assess its preliminary design and safety features. Tritium transport and permeation are complex phenomena to be
Candido, Luigi, Testoni, Raffaella, Utili, Marco, Zucchetti, Massimo   +3 more
openaire   +1 more source

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

Fusion Engineering and Design, 2018
Abstract 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).
Froio, Antonio, Bertinetti, Andrea, Ciattaglia, Sergio, Cismondi, Fabio, Savoldi, Laura, Zanino, Roberto   +5 more
openaire   +2 more sources

Neutronics Simulations for DEMO Diagnostics. [PDF]

Sensors (Basel), 2023
Luís R, Nietiadi Y, Quercia A, Vale A, Belo J, Silva A, Gonçalves B, Malaquias A, Gusarov A, Caruggi F, Perelli Cippo E, Chernyshova M, Bienkowska B, Biel W.   +13 more
europepmc   +1 more source

Implications of T loss in first wall armor and structural materials on T-self-sufficiency in future burning fusion devices

Nuclear Fusion
Future fusion reactors will have to breed enough tritium (T) to sustain continuous operation and to produce excess T to power up other fusion reactors. Therefore, T is a scarce resource that must not be lost inside the fusion power plants systems.
K. Schmid, T. Schwarz-Selinger, R. Arredondo, A. Theodorou, T. Pomella Lobo   +4 more
doaj   +1 more source

Breeding blanket mock-up testing in IFMIF-DONES

Nuclear Fusion
The fusion community is looking for solutions to qualify the breeding blankets (BB) before their final testing in DEMO. Thus, ambitious and attractive proposals, like the Volumetric Neutron Source, are being explored.
D. Rapisarda, P. Arena, F. Arranz, B. Brañas, F. Mota, M.I. Ortiz, A. Serikov, G. Zhou   +7 more
doaj   +1 more source