Results 41 to 50 of about 286 (97)

Main Nuclear Responses of the DEMO Tokamak with Different In-Vessel Component Configurations

Applied Sciences
Research and development of the DEMOnstration power plant (DEMO) breeder blanket (BB) has been performed in recent years based on a predefined DEMO tritium breeding ratio (TBR) requirement, which determines a loss of wall surface due to non-breeding in ...
Jin Hun Park, Pavel Pereslavtsev
doaj   +1 more source

On the Use of RELAP5/Mod3.3 Numerical Tool to Support the Design of the WCLL BB and BoP on the Path for Exploiting Fusion Energy

Nuclear Technology
EUROfusion, the European consortium for fusion research, coordinates and funds Research and Development (R&D) activities as part of a long-term road map toward achieving commercial fusion energy, primarily through projects like ITER and its successor, DEMO.
Alessandra Vannoni, Cristiano Ciurluini, Giorgio Mongiardini, Francesco Colliva, Tommaso Del Moro, Marcello Principato, Lorenzo Melchiorri, Alessandro Tassone, Bruno Gonfiotti, Pietro Arena, Marica Eboli, Fabio Giannetti, Gianfranco Caruso, Amelia Tincani, Alessandro Del Nevo   +14 more
openaire   +2 more sources

Helical-shaped double wall tubes solution for the breeding zone cooling in the WCLL breeding blanket [PDF]

One of the two most promising Breeding Blanket (BB) concepts to be chosen as driver design of the EU-DEMO fusion reactor is the Water-Cooled Lead Lithium (WCLL) BB. A crucial point of this key component is the cooling of the BB structural elements and of
Arena P., Maccari P., Del Nevo A., Noce S., Moro F., Marinari R.   +5 more
core   +1 more source

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

, 2020
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 ...
Federici G., Ciattaglia S., Moscato I., Cismondi F., Del Nevo A., Chiovaro P., Di Maio P. A., Spagnuolo G. A., Vallone E.   +8 more
core   +1 more source

RELAP5-based thermal-hydraulic assessment of the STEAM facility for DEMO WCLL balance of plant analysis [PDF]

DEMO power station aims to demonstrate the generation of hundred MWs of electrical power from fusion reactions, then transmitted from the Tokamak reactor to the grid through the Balance of Plant (BoP).
Alessandra Vannoni, Alessandro Del Nevo, Diego Jaramillo Sierra, Cristiano Ciurluini, Marica Eboli, Fabio Giannetti, Pierdomenico Lorusso   +6 more
core   +4 more sources

Thermal-hydraulic analysis of WCLL BB First-Wall mock-up in Water Loop facility under transient conditions

Fusion Engineering and Design
The EUropean DEMOnstration Power Plant (EU-DEMO) represents a milestone in nuclear fusion research, serving as crucial step towards the realization of commercial fusion energy production by bridging the gap between current research efforts and future industrial-scale deployment.
Mongiardini, G., Vannoni, A., Ciurluini, C., Maccari, P., Gonfiotti, B., Arena, P., Eboli, M., Giannetti, F., Nevo, A. Del   +8 more
openaire   +1 more source

Optimized Water Distillation Layout for Detritiation Purpose

Applied Sciences
Tritium permeation constitutes a key issue for the future EU-DEMO, especially in the Breeding Blanket (BB) where fusion energy must be delivered to the Primary Heat Transport System (PHTS) and where tritium must be bred.
Vincenzo Narcisi, Alessia Santucci
doaj   +1 more source

On the effects of the Double-Walled Tubes lay-out on the DEMO WCLL breeding blanket module thermal behavior [PDF]

, 2019
The EU-DEMO Water-Cooled Lithium Lead Breeding Blanket (WCLL BB) concept foresees liquid Pb-15.7Li eutectic alloy as breeder and neutron multiplier, whereas pressurized subcooled water as coolant, with operative conditions typical of the PWR fission ...
Arena P., Del Nevo A., Di Maio P. A., Forte R.   +3 more
core   +1 more source

The chemical compatibility of oxide ceramic candidates in static PbLi for advanced breeding blanket channel components

Nuclear Materials and Energy
The use of a PbLi eutectic alloy is extended in the Dual Coolant Lead Lithium (DCLL) and Water Coolant Lead Lithium (WCLL) Breeding Blanket (BB) design concepts in future fusion reactors.
J. Patiño, J.M García, G.D. Soria, M. González   +3 more
doaj   +1 more source

Investigation on MELCOR Code Capabilities for the Simulation of Lithium–Lead Chemical Interactions for Fusion Safety Applications

Energies
In the WCLL-BB liquid blanket concept, among the postulated accidental scenarios to be investigated regarding the PbLi system, a loss of liquid metal is one of the most crucial for safety purposes.
Francesco Galleni, Vittorio Cossu, Marigrazia Moscardini, Nicola Forgione   +3 more
doaj   +1 more source