Results 41 to 50 of about 513 (179)

Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket

open access: yesFusion Engineering and Design, 2018
Abstract In the frame of EUROfusion Work Package Breeding Blanket, thermal-hydraulic engineering analyses were carried out at ENEA Brasimone, in close cooperation with Sapienza University of Rome, to investigate thermal and fluid-dynamic behavior of the Water Cooled Lithium Lead Breeding Blanket, which is a candidate option for the European DEMO ...
Martelli, Emanuela   +3 more
openaire   +1 more source

Advancements in Designing the DEMO Driver Blanket System at the EU DEMO Pre-Conceptual Design Phase: Overview, Challenges and Opportunities

open access: yesJournal of Nuclear Engineering, 2023
The EU conducted the pre-conceptual design (PCD) phase of the demonstration reactor (DEMO) during 2014–2020 under the framework of the EUROfusion consortium.
Francisco A. Hernández   +9 more
doaj   +1 more source

R&D Needs for the Design of the EU-DEMO HCPB ICD Balance of Plant in FP9

open access: yesJournal of Nuclear Engineering, 2022
During the Pre-Conceptual Design Phase of the EU-DEMO, two BOP solutions for WCLL and HCPB were elaborated, as close as possible to industrial standards.
Sara Perez-Martin   +3 more
doaj   +1 more source

Listening to Our Patients, at Last?

open access: yes, 1995
Canadian Respiratory Journal, Volume 2, Issue 4, Page 203-203, 1995.
Norman L Jones
wiley   +1 more source

Long-term corrosion behavior of ODS-Eurofer in flowing Pb-15.7Li at 550°C

open access: yesNuclear Materials and Energy, 2016
Low activation ferritic-martensitic steels (RAFM-steels) are foreseen as structural materials in different blanket designs (HCLL, DCLL, WCLL) with Pb-15.7Li as breeding and partly also as cooling medium.
W. Krauss, S.-E. Wulf, J. Konys
doaj   +1 more source

Hp and pH: Implications for the Eradication of Heliobacter pylori

open access: yes, 1993
Canadian Journal of Gastroenterology and Hepatology, Volume 7, Issue 5, Page 406-410, 1993.
Richard H Hunt
wiley   +1 more source

Preliminary estimates of tritium permeation and retention in the first wall of DEMO due to ion bombardment

open access: yesNuclear Materials and Energy, 2021
Tritium self-sufficiency presents a critical engineering challenge for DEMO, requiring efficient breeding and extraction systems, as well as minimizing tritium losses to the surrounding systems, such as plasma-facing components, vacuum vessel, cooling ...
R. Arredondo   +3 more
doaj   +1 more source

Manufacturing of PAV-ONE, a Permeator against Vacuum Mock-Up with Niobium Membrane

open access: yesEnergies, 2023
The Permeator Against Vacuum (PAV) is one of the proposed technologies for the Tritium Extraction System of the WCLL BB (Water-Cooled Lithium-Lead Breeding Blanket) of the EU DEMO reactor.
Francesca Papa   +8 more
doaj   +1 more source

Activities in Divertor Reflector and Linear Plates Using WCLL and HCPB Breeding Blanket Concepts

open access: yesEnergies, 2021
In fusion devices, such as European Demonstration Fusion Power Reactor (EU DEMO), primary neutrons can cause material activation due to the interaction between the source particles and the targeting material.
Simona Breidokaite, Gediminas Stankunas
doaj   +1 more source

Water-cooled lead and ceramic breeder (WLCB) breeding blanket (BB) for the EU DEMO: Neutronic campaigns for T breeding optimization

open access: yesNuclear Materials and Energy
A novel Breeding Blanket (BB) concept, the Water-cooled Lead and Ceramic Breeder (WLCB) BB, has been developed under the EUROfusion Programme to address key challenges identified during the Pre-Conceptwual Design (PCD) phase for the driver BB concepts ...
Iole Palermo   +6 more
doaj   +1 more source

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