Results 1 to 10 of about 140 (98)

Conceptual Design of the Steam Generators for the EU DEMO WCLL Reactor

open access: yesEnergies, 2023
In the framework of the EUROfusion Horizon Europe Programme, ENEA and its linked third parties are in charge of the conceptual design of the steam generators belonging to EU DEMO WCLL Breeding Blanket Primary Heat Transfer Systems (BB PHTSs). In particular, in 2021, design activities and supporting numerical simulations were carried out in order to ...
Amelia Tincani   +11 more
doaj   +6 more sources

The Design of Water Loop Facility for Supporting the WCLL Breeding Blanket Technology and Safety

open access: yesEnergies, 2023
The WCLL Breeding Blanket of DEMO and the Test Blanket Module (TBM) of ITER require accurate R&D activities, i.e., concept validation at a relevant scale and safety demonstrations. In view of this, the strategic objective of the Water Loop (WL) facility, belonging to the W-HYDRA experimental platform planned at C.R.
Alessandra Vannoni   +16 more
doaj   +8 more sources

Design of a Test Section for the Experimental Investigation of the WCLL Manifold Hydraulic Features

open access: yesEnergies, 2023
A scaled-down test section representative of an Outboard Segment manifold of the Water-Cooled Lithium Lead Breeding Blanket for the European DEMO has been designed for installation and test in a high- mass flow branch of the W-HYDRA facility, under construction at the premises of ENEA Brasimone Research Center.
Aldo Collaku   +4 more
doaj   +5 more sources

Embrittlement of WCLL blanket and its fracture mechanical assessment

open access: yesNuclear Fusion, 2023
Abstract In the European fusion programme, the Water Cooled Lithium Lead breeding blanket (WCLL BB) uses EUROFER as a structural material cooled with water at temperatures between 295 °C–328 °C and a pressure of 155 bar. The WCLL BB will be significantly irradiated (>2 dpa), while some parts will not receive significant heat loads, e ...
Aktaa J.   +7 more
openaire   +5 more sources

Design of the Test Section for the Experimental Validation of Antipermeation and Corrosion Barriers for WCLL BB

open access: yesApplied Sciences, 2022
Tritium permeation into the Primary Heat Transfer System (PHTS) of DEMO and ITER reactors is one of the challenging issues to be solved in order to demonstrate the feasibility of nuclear fusion power plants construction.
Marco Utili   +5 more
doaj   +3 more sources

Analysis of the Thermo-Mechanical Behaviour of the EU DEMO Water-Cooled Lithium Lead Central Outboard Blanket Segment under an Optimized Thermal Field

open access: yesApplied Sciences, 2022
Within the framework of the EUROfusion research activities on the DEMO Water-Cooled Lithium Lead (WCLL) Breeding Blanket (BB) design, a research study was performed to preliminarily optimize, from the thermal point of view, the WCLL Central Outboard ...
Ilenia Catanzaro   +2 more
doaj   +1 more source

Advancements in DEMO WCLL breeding blanket design and integration

open access: yesInternational Journal of Energy Research, 2018
The water-cooled lithium–lead breeding blanket is a candidate option for the European Demonstration Power Plant(DEMO) nuclear fusion reactor. This breeding blanket concept relies on the liquid lithium– lead as breeder–multiplier,pressurized water as coolant, and EUROFER as structural material.
Martelli, E.   +16 more
  +9 more sources

Neutronic Activity for Development of the Promising Alternative Water-Cooled DEMO Concepts

open access: yesApplied Sciences, 2023
An emerging breeding blanket that fulfills performance criteria, meets the safety requirements, and is reliable enough to meet the plant availability is a challenging issue that assumes complex studies involving numerous neutronic analyses based on the ...
Pavel Pereslavtsev   +3 more
doaj   +1 more source

NUCLEAR DATA SENSITIVITY/UNCERTAINTY PRE-ANALYSIS OF FNG WCLL FUSION BENCHMARK [PDF]

open access: yesEPJ Web of Conferences, 2021
To assure tritium self-sufficiency in future fusion reactors such as DEMO the accuracy of TRP calculations has to be demonstrated within the design uncertainties.
Kodeli Ivan A.   +2 more
doaj   +1 more source

The DEMO Water-Cooled Lead–Lithium Breeding Blanket: Design Status at the End of the Pre-Conceptual Design Phase

open access: yesApplied Sciences, 2021
The Water-Cooled Lead–Lithium Breeding Blanket (WCLL BB) is one of the two blanket concept candidates to become the driver blanket of the EU-DEMO reactor. The design was enacted with a holistic approach. The influence that neutronics, thermal-hydraulics (
Pietro Arena   +15 more
doaj   +1 more source

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