Results 81 to 90 of about 1,037 (124)
W-HYDRA: a new experimental platform for the Water-Cooled Lead Lithium Breeding Blanket
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 +14 more
doaj +1 more source
Magnetohydrodynamic simulation of the WCLL breeding blanket with helical cooling pipes
The Water-Cooled Lead Lithium (WCLL) is a Breeding Blanket (BB) concept presently in the development phase for implementation in the DEMO fusion reactor demonstrator. The Lead lithium eutectic alloy (PbLi) breeder is moved at a slow velocity to diminish Magnetohydrodynamics (MHD) pressure losses.
Alessandro Tassone, Simone Siriano
openaire +1 more source
Parametric thermal-hydraulic analysis of the EU DEMO Water-Cooled Lithium-Lead First Wall using the GETTHEM code [PDF]
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 +4 more
core +1 more source
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 +4 more
openaire +3 more sources
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. +8 more
openaire +4 more sources
Design and construction of experimental device for verifying the solubility of helium in liquid metals [PDF]
Palivová soběstačnost budoucích fúzních elektráren je jeden z klíčových problémů, který je nutno vyřešit k úspěšnému energetickému využití termojaderné fúze. Tento problém lze vyřešit zahrnutím breeding blanketu, jehož koncepty jsou však stále ve vývoji.
Tomáš Svoboda
core
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 +4 more
doaj +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. +3 more
core +1 more source
Neutronics Simulations for DEMO Diagnostics. [PDF]
Luís R +13 more
europepmc +1 more source
Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review. [PDF]
Alba R, Iglesias R, Cerdeira MÁ.
europepmc +1 more source

