Zobrazeno 1 - 10
of 1 026
pro vyhledávání: '"Breeding blanket"'
Publikováno v:
Nuclear Materials and Energy, Vol 39, Iss , Pp 101682- (2024)
The use of a PbLi eutectic alloy is extended in the Dual Coolant Lead Lithium (DCLL) and Water Coolant Lead Lithium (WCLL) Breeding Blanket (BB) design concepts in future fusion reactors. However, the reactivity of PbLi is a challenging problem, as t
Externí odkaz:
https://doaj.org/article/5d5e481ebd0f46269a954e1e6929420a
The effect of Li2TiO3 pebbles on the mechanical properties of ARAA under breeding blanket conditions
Publikováno v:
Nuclear Materials and Energy, Vol 39, Iss , Pp 101658- (2024)
The breeding blanket serves as a critical element for achieving a self-sustaining tritium cycle and generating sufficient energy in fusion reactors. This study focuses on candidate materials of the helium-cooled solid breeder blanket designed for a d
Externí odkaz:
https://doaj.org/article/cf4b960a761c4bcb886d91f9794dc2d5
Publikováno v:
Nuclear Materials and Energy, Vol 38, Iss , Pp 101581- (2024)
The current development with respect to modifying the ECX (electrochemical X-deposition) process towards thicker alumina formed by heat treatment of aluminium electroplated on steel is described. As anticipated, changing the heat treatment atmosphere
Externí odkaz:
https://doaj.org/article/c3fa37b90ccc4f158c938c9ba53017d7
Autor:
Francisco A. Hernández, Pietro Arena, Lorenzo V. Boccaccini, Ion Cristescu, Alessandro Del Nevo, Pierre Sardain, Gandolfo A. Spagnuolo, Marco Utili, Alessandro Venturini, Guangming Zhou
Publikováno v:
Journal of Nuclear Engineering, Vol 4, Iss 3, Pp 565-601 (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. The current strategy of DEMO design is to bridge the breeding blanket (BB) technology gaps
Externí odkaz:
https://doaj.org/article/473d0c22e2af45959dc203cb2f6ce123
Publikováno v:
Mechanical Engineering Journal, Vol 11, Iss 2, Pp 23-00416-23-00416 (2023)
In the framework of the development of fusion energy, one of the most prominent technologies arising to address the issues of tritium breeding and power conversion is the Water-Cooled Lithium-Lead (WCLL). This technology utilizes a molten eutectic al
Externí odkaz:
https://doaj.org/article/a366978355f84aa89aadd5861e364d93
Publikováno v:
Journal of Nuclear Engineering, Vol 4, Iss 1, Pp 165-176 (2023)
The outcome of the electromagnetic (EM) analyses carried out during the DEMO pre-conceptual phase demonstrated that EM loads are relevant for the structural assessment of the breeding blanket (BB) and, in particular, for the definition of the boundar
Externí odkaz:
https://doaj.org/article/c897fd82c7c748a89380095964344a87
Autor:
I. Fernández-Berceruelo, I. Palermo, F.R. Urgorri, D. Rapisarda, M. González, J. Alguacil, J.P. Catalán, J.M. García, J. Kekrt, M. Kordač, I. Krastiņš, T. Melichar, J.Á. Noguerón, E. Platacis, R. Petráš, M. Roldán, A. Rueda, J. Serna, D. Sosa, D. Suàrez
Publikováno v:
Nuclear Fusion, Vol 64, Iss 5, p 056029 (2024)
There is no doubt about the interest of achieving as fast as possible the capability to build and operate high performance reactors that finally allow fusion competing in the electricity market. An advanced breeding blanket based on the Dual Coolant
Externí odkaz:
https://doaj.org/article/36d31bc09a994308a6a8476c8500c27b
Autor:
P. Arena, A. Del Nevo, M. Eboli, B. Gonfiotti, P. Maccari, R. Marinari, A. Tincani, N. Badodi, G. Bongiovì, I. Catanzaro, F. Galleni, C. Risi, L.L. Sanasi, A. Tarallo, A. Vannoni
Publikováno v:
Nuclear Fusion, Vol 64, Iss 7, p 076043 (2024)
In the framework of the activities coordinated by the EUROfusion consortium, the Water thermal-HYDRAulic (W-HYDRA) experimental platform is being built at the ENEA Brasimone Research Centre in order to support the development of the Water-Cooled Lead
Externí odkaz:
https://doaj.org/article/13cbc2c1fa064df48fb78a1c2b0abe6b
Autor:
Rocco Mozzillo, Christian Bachmann, Pierluigi Fanelli, Guenter Janeschitz, Thomas Steinbacher
Publikováno v:
Heliyon, Vol 9, Iss 8, Pp e18926- (2023)
The maintenance of the DEMO Breeding Blanket (BB) remotely is a crucial aspect in development of the DEMO power plant. It is a challenge due to the huge mass of the BB segment of about 180 tons. A new concept for the BB transporter has recently been
Externí odkaz:
https://doaj.org/article/4f933cda26874dfeb88851988280d592
Publikováno v:
Journal of Nuclear Engineering, Vol 3, Iss 4, Pp 409-420 (2022)
In the design of magnetic confinement nuclear fusion power plants, the breeding blanket (BB) plays a crucial role since it must fulfil key functions such as tritium breeding, radiation-shielding, and removal of the heat power generated by the plasma.
Externí odkaz:
https://doaj.org/article/8af4fea880a74aa3ae3efa556df1f930