Results 81 to 90 of about 1,034 (139)

Activated corrosion product contamination assessments of DEMO WCLL breeding blanket primary heat transport system

Fusion Engineering and Design
In water-cooled fusion reactors, the assessment of the primary system contamination is essential for waste management, machine availability, occupational radiation exposure, and radiological hazard determination. The primary cooling water is not only directly activated by the intense neutron field but is a contamination vector for a significant variety
Terranova, Nicholas, Chiovaro, Pierluigi, Dacquait, Frédéric, Moscato, Ivo, Vallone, Eugenio   +4 more
openaire   +3 more sources

Parametric thermal-hydraulic analysis of the EU DEMO Water-Cooled Lithium-Lead First Wall using the GETTHEM code [PDF]

, 2018
The system-level code GETTHEM is applied to the thermal-hydraulic analysis of an entire segment of the Water-Cooled Lithium-Lead (WCLL) First Wall (FW) of the EU DEMO reactor, parametrically varying the heat load of the FW and the coolant mass flow rate.
Del Nevo, Alessandro, Froio, Antonio, Martelli, Emanuela, Savoldi, Laura, Zanino, Roberto   +4 more
core   +1 more source

Development of load specifications for the design of the breeding blanket system [PDF]

, 2020
The Breeding Blanket (BB) system with a volume of about 1700m(3) and a plasma front surface of about 1400m(2) represents the largest In-Vessel component of DEMO reactor. Due to its position and its key functions (e.g.
Boccaccini L. V., Bongiovì G., Cismondi F., Maione I. A., Spagnuolo G. A.   +4 more
core   +1 more source

Assessment of DEMO WCLL breeding blanket primary heat transfer system isolation valve absorbed doses due to activated water

Fusion Engineering and Design, 2020
Abstract Within the framework of the activities foreseen by the EUROfusion action on the cooling water activation assessment for a DEMO reactor equipped with a Water Cooled Lithium Lead Breeding Blanket (WCLL BB), the University of Palermo is involved in the investigation of the absorbed dose induced by the decay of nitrogen radioisotopes produced by
Chiovaro, P., Ciattaglia, S., Cismondi, F., Del Nevo, A., Di Maio, P.A., Federici, G., Moscato, I., Spagnuolo, G.A., Vallone, E.   +8 more
openaire   +4 more sources

Parametric study of the influence of double-walled tubes layout on the DEMO WCLL breeding blanket thermal performances

Fusion Engineering and Design, 2020
Abstract Within the framework of the EUROfusion activities regarding the EU-DEMO Breeding Blanket (BB) concept, the University of Palermo is long-time involved, in close cooperation with ENEA, in the design of the Water Cooled Lithium Lead (WCLL) BB, that is one of the two concepts under consideration for the DEMO reactor.
Catanzaro, Ilenia, Arena, Pietro, Del Nevo, Alessandro, Di Maio, Pietro Alessandro, Edemetti, Francesco, Forte, Ruggero, Martelli, Emanuela   +6 more
openaire   +3 more sources

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

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

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review. [PDF]

Materials (Basel), 2022
Alba R, Iglesias R, Cerdeira MÁ.
europepmc   +1 more source

System code simulation of DEMO WCLL central outboard blanket equatorial cell operational transients [PDF]

Within the framework of EUROfusion FP8 and FP9 research activities, an important work was carried out to optimize the DEMO Breeding Blanket (BB) layout. The blanket concept selected to be investigated in this work is the Water-Cooled Lead-Lithium (WCLL).
Ciurluini C., Del Nevo A., Giannetti F., Principato M.   +3 more
core   +1 more source

Numerical investigation of the structural performances of the EU-DEMO Water-Cooled Lead Lithium breeding blanket equipped with helicoidal double-walled tubes [PDF]

With the aim of improving the EU-DEMO breeding blanket (BB) system performances, variants to the reference design are presently under investigation in the EUROfusion activities.
Arena P., Bongiovì G., Catanzaro I., Chiovaro P., Di Maio P. A., Fernandez-Berceruelo I., Giambrone S., Nogueron J. A., Quartararo A., Vallone E.   +9 more
core   +1 more source