Zobrazeno 1 - 10
of 69
pro vyhledávání: '"Giacomo Aiello"'
Autor:
Jarir Aktaa, Ermile Gaganidze, Gaetano Bongioví, Pietro Arena, Gandolfo Alessandro Spagnuolo, Giacomo Aiello, Pierluigi Chiovaro, Christian Bachmann
Publikováno v:
Nuclear Fusion, Vol 63, Iss 9, p 096016 (2023)
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
Externí odkaz:
https://doaj.org/article/5f6c65c1df414bdfa2eb27ef8a9b63e0
Autor:
Michael Rieth, Michael Dürrschnabel, Simon Bonk, Ute Jäntsch, Thomas Bergfeldt, Jan Hoffmann, Steffen Antusch, Esther Simondon, Michael Klimenkov, Carsten Bonnekoh, Bradut-Eugen Ghidersa, Heiko Neuberger, Jörg Rey, Christian Zeile, Gerald Pintsuk, Giacomo Aiello
Publikováno v:
Applied Sciences, Vol 11, Iss 24, p 11653 (2021)
Plasma facing components for energy conversion in future nuclear fusion reactors require a broad variety of different fabrication processes. We present, along a series of studies, the general effects and the mutual impact of these processes on the pr
Externí odkaz:
https://doaj.org/article/669400a9454f443b98974e9480a5cd96
Autor:
Michael Rieth, T. Nozawa, Giacomo Aiello, J. Henry, M. Gorley, Hiroyasu Tanigawa, Gerald Pintsuk
Publikováno v:
Fusion Engineering and Design
Fusion Engineering and Design, 170, Art.-Nr.: 112513
Fusion Engineering and Design, 170, Art.-Nr.: 112513
This work addresses an overview of the recent progress, associated risks and development plans of structural materials for in-vessel components (IVCs) in DEMO plants. Reduced Activation Ferritic Martensitic Steels form the primary structural material
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4de2cc57c3099d2701bc70d8265b8704
Autor:
Heiko Neuberger, Michael Rieth, Bradut-Eugen Ghidersa, Jörg Rey, E. Simondon, Michael Dürrschnabel, Giacomo Aiello, Simon Bonk, N. De Wispelaere, Christian Zeile, Y. de Carlan, J. Henry, Jan Hoffmann, Gerald Pintsuk
Publikováno v:
Fusion Engineering and Design
Fusion Engineering and Design, 2021, 166, pp.112275. ⟨10.1016/j.fusengdes.2021.112275⟩
Fusion engineering and design 166, 112275-(2021). doi:10.1016/j.fusengdes.2021.112275
Fusion Engineering and Design, 166, Art.-Nr.: 112275
Fusion Engineering and Design, 2021, 166, pp.112275. ⟨10.1016/j.fusengdes.2021.112275⟩
Fusion engineering and design 166, 112275-(2021). doi:10.1016/j.fusengdes.2021.112275
Fusion Engineering and Design, 166, Art.-Nr.: 112275
A major part in the EUROfusion materials research program is dedicated to characterize and quantify nuclear fusion specific neutron damage in structural materials. While the majority of irradiation data gives a relatively clear view on the displaceme
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::60110e5cb2a686ed3a6afeac9d670831
https://hal-cea.archives-ouvertes.fr/cea-03850184
https://hal-cea.archives-ouvertes.fr/cea-03850184
Autor:
Jan Hoffmann, N. De Wispelaere, Gerald Pintsuk, Michael Rieth, Y. de Carlan, J. Henry, Michael Dürrschnabel, Steffen Antusch, Christian Zeile, Jörg Rey, Bradut-Eugen Ghidersa, Heiko Neuberger, Giacomo Aiello, Simon Bonk, E. Simondon
Publikováno v:
Nuclear fusion 61(11), 116067-(2021). doi:10.1088/1741-4326/ac2523
Nuclear fusion, 61 (11), 116067
Nuclear fusion, 61 (11), 116067
In future nuclear fusion reactors, plasma facing components have to sustain specific neutron damage. While the majority of irradiation data provides a relatively clear picture of the displacement damage, the effect of helium transmutation is not yet
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::1d94c2fc34086c7b0a417e586bf6ed01
Autor:
A. Del Nevo, Luis Maqueda, Fernando Rueda, T. Batal, David Alonso, E. Rodríguez, Julien Aubert, M. Soldaini, A. Morin, Fabio Cismondi, Rémi Boullon, S. Burles, Joelle Vallory, Giacomo Aiello, B. Cantone
Publikováno v:
Fusion Engineering and Design
Fusion Engineering and Design, Elsevier, 2020, 160, pp.111921-. ⟨10.1016/j.fusengdes.2020.111921⟩
Fusion Engineering and Design, 2020, 160, pp.111921. ⟨10.1016/j.fusengdes.2020.111921⟩
Fusion Engineering and Design, Elsevier, 2020, 160, pp.111921-. ⟨10.1016/j.fusengdes.2020.111921⟩
Fusion Engineering and Design, 2020, 160, pp.111921. ⟨10.1016/j.fusengdes.2020.111921⟩
International audience; In the European strategy, DEMO is the intermediate step between ITER and a commercial fusion power plant. In this framework, one of the goal of DEMO is to be a Breeding Blanket test facility. The Breeding Blanket, which is not
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c641d8148752690dc18f5c85beff5400
https://hal.archives-ouvertes.fr/hal-03491638
https://hal.archives-ouvertes.fr/hal-03491638
Publikováno v:
Fusion Engineering and Design
Fusion Engineering and Design, 2020, 153, pp.111514-. ⟨10.1016/j.fusengdes.2020.111514⟩
Fusion Engineering and Design, Elsevier, 2020, 153, pp.111514-. ⟨10.1016/j.fusengdes.2020.111514⟩
Fusion Engineering and Design, 2020, 153, pp.111514-. ⟨10.1016/j.fusengdes.2020.111514⟩
Fusion Engineering and Design, Elsevier, 2020, 153, pp.111514-. ⟨10.1016/j.fusengdes.2020.111514⟩
The pre-conceptual design of the DEMOnstration reactors has already started and several tokamak configurations have to be tested to find the best design by exploring different design parameters. Fast simulations involving the different components beh
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::87bd434408fb94929abed77f55cc621e
https://hal.science/hal-03489858/file/S0920379620300624.pdf
https://hal.science/hal-03489858/file/S0920379620300624.pdf
Publikováno v:
Fusion Engineering and Design
The pre-concept design of the DEMO Vacuum Vessel is going on in view of the 2020 gate review; moreover the nuclear heat loads on the vessel inner shell were determined and found to be about one order of magnitude higher compared to ITER. A subsequent
Autor:
Julien Aubert, Giacomo Aiello, Jean-Charles Jaboulay, A. Morin, Rémi Boullon, Justine Peyraud
Publikováno v:
Fusion Engineering and Design
Fusion Engineering and Design, 2018, 136, pp.1231-1236. ⟨10.1016/j.fusengdes.2018.04.107⟩
Fusion Engineering and Design, 2018, 136, pp.1231-1236. ⟨10.1016/j.fusengdes.2018.04.107⟩
In the framework of the European “HORIZON 2020” research program, the EUROfusion Consortium develops a design of a fusion demonstrator (DEMO). The Breeding Blanket (BB) directly surrounding the plasma is a major component ensuring tritium self-su
Publikováno v:
Fusion Engineering and Design. 136:7-11
Thermohydraulic measurements in liquid metal test blanket modules for ITER require reliable sensors for detection of temperature and magnetohydrodynamic properties of the flow such as the distribution of electric potential. The latter one can be dire