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

Autor: R. Arredondo, K. Schmid, F. Subba, G.A. Spagnuolo

Publikováno v: Nuclear Materials and Energy, Vol 28, Iss , Pp 101039- (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, coolin

Externí odkaz: https://doaj.org/article/84d55d6d12e54424b2ff20ddffffb1f4

Structural assessment of the EU-DEMO water-cooled lead lithium central outboard blanket segment adopting the sub-modelling technique

Autor: I. Catanzaro, G. Bongiovì, P.A. Di Maio, P. Arena, G.A. Spagnuolo

Publikováno v: Fusion Engineering and Design. 192:113601

The development of a sound conceptual design of the Water-Cooled Lead Lithium Breeding Blanket (WCLL BB) is pivotal to make a breakthrough towards the selection of the driver blanket concept for the EU-DEMO. To achieve this goal, an intense research

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::dcd21b8eeed221748446a25d7d197065
https://doi.org/10.1016/j.fusengdes.2023.113601

Status of maturation of critical technologies and systems design: Breeding blanket

Autor: L.V. Boccaccini, F. Arbeiter, P. Arena, J. Aubert, L. Bühler, I. Cristescu, A. Del Nevo, M. Eboli, L. Forest, C. Harrington, F. Hernandez, R. Knitter, H. Neuberger, D. Rapisarda, P. Sardain, G.A. Spagnuolo, M. Utili, L. Vala, A. Venturini, P. Vladimirov, Guangming Zhou

Publikováno v: Fusion Engineering and Design
Fusion Engineering and Design, 2022, 179, pp.113116. ⟨10.1016/j.fusengdes.2022.113116⟩
Fusion Engineering and Design, 179, Art.Nr. 113116

International audience; The scope of the EUFOfusion Work Package Breeding Blanket is to develop a blanket concept for the EU DEMO reactor; this includes the blanket segments inside the Vacuum Vessel and the related Tritium Extraction/Removal Systems.

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b5fbee72fae5165becbe3ac15dcf3c38
https://cea.hal.science/cea-03649326

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Production and transport modelling of Po-210 in DEMO reactor

Autor: P. Chiovaro, A. Quartararo, S. Basile, S. Ciattaglia, P.A. Di Maio, F. Moro, I. Moscato, G.A. Spagnuolo

Publikováno v: Nuclear Fusion. 62:056022

One of the generic designs of the nuclear fusion DEMO reactor proposed by the EUROfusion consortium foresees the development of a tritium breeding blanket (BB) relying on the use of the liquid-metal PbLi eutectic alloy as both neutron multiplier and

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8fdc0ea99b6e1effd09d7e3df88a4991
https://doi.org/10.1088/1741-4326/ac548a