Results 11 to 20 of about 201,032 (307)
Neutronic analysis in the HCLL blanket module has been established, and the calculation was performed by the ITER team, including the first wall (FW). In this study, seven materials have been investigated for FW material by considering characteristics ...
Indah Rosidah Maemunah +3 more
doaj +1 more source
Design of the CIEMAT Corrosion Loop for Liquid Metal Experiments
The main components of a liquid breeder blanket in a fusion power reactor are lead lithium alloy (PbLi) and the steel structure in which the liquid is enclosed (EUROFER). Several compatibility tests have shown that structural materials always suffer from
Elisabetta Carella +2 more
doaj +1 more source
Effect on impact properties of adding tantalum to V-4Cr-4Ti ternary vanadium alloy
Four V-Ta-4Cr-4Ti quaternary alloys containing different quantities of Ta were investigated to determine the effect of Ta content on the Charpy impact properties.
Takeshi Miyazawa +9 more
doaj +1 more source
The contribution of ENEA together with Rina-CSM to the Eurofusion programme “WPMAT-Advanced Seels” deals with the development of innovative RAFM steels able to withstand the critical temperatures typical of the different operational environments foreseen
C. Cristalli +3 more
doaj +1 more source
Resistance to frost of road pavement structure is ensured by a functional frost blanket course from frost nonsusceptible soils or aggregate mixtures. The material used and the thickness of frost blanket course must not only ensure the required resistance
Audrius Vaitkus +4 more
doaj +1 more source
The investigation of the neutronic responses of components in the K-DEMO
The neutronic response of consisting materials of the Korean fusion DEMOnstration reactor (K-DEMO) in its fusion neutron environment is a crucial consideration factor from the conceptual design stage of the K-DEMO.
Byung Chul Kim
doaj +1 more source
IFMIF suitability for evaluation of fusion functional materials [PDF]
The International FusionMaterials Irradiation Facility (IFMIF) is a future neutron source based on the D-Li stripping reaction, planned to test candidate fusionmaterials at relevant fusion irradiation conditions.
A. García +25 more
core +2 more sources
Blanket materials for dt fusion reactors [PDF]
Abstract This paper presents an overview of the critical materials issues that must be considered in the development of a tritium breeding blanket for a tokamak fusion reactor that operates on the D-T-Li fuel cycle. The primary requirements of the blanket system are identified and the important criteria that must be considered in the development of ...
openaire +1 more source
Fusion energy: technological challenges [PDF]
This paper presents an overview of the main technological challenges of magnetic confinement fusion. Many of the challenges are being addressed in the context of the ITER construction and exploitation.
Romanelli Francesco
doaj +1 more source
The paper examines an object that was found under the floorboards of a Sviyazhsk house in 2018. During the study, the object was identified as a blanket with a painted layer; the affiliation, time of manufacture and prototype of the painting were also ...
Anastasia S. Lisina +2 more
doaj +1 more source

