|
1
|
Acampora E, Ambrosino R, Castaldo A, Iervolino R. Magnetic control of DTT alternative plasma configurations. Fusion Engineering and Design 2023. [DOI: 10.1016/j.fusengdes.2023.113617] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 03/08/2023]
|
|
2
|
Biel W, Ariola M, Bolshakova I, Brunner K, Cecconello M, Duran I, Franke T, Giacomelli L, Giannone L, Janky F, Krimmer A, Luis R, Malaquias A, Marchiori G, Marchuk O, Mazon D, Pironti A, Quercia A, Rispoli N, Shawish SE, Siccinio M, Silva A, Sozzi C, Tartaglione G, Todd T, Treutterer W, Zohm H. Development of a concept and basis for the DEMO diagnostic and control system. Fusion Engineering and Design 2022; 179:113122. [DOI: 10.1016/j.fusengdes.2022.113122] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
|
|
3
|
Kembleton R, Siccinio M, Maviglia F, Militello F. Benefits and Challenges of Advanced Divertor Configurations in DEMO. Fusion Engineering and Design 2022; 179:113120. [DOI: 10.1016/j.fusengdes.2022.113120] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
|
|
4
|
Castaldo A, Albanese R, Ambrosino R, Crisanti F. Plasma Scenarios for the DTT Tokamak with Optimized Poloidal Field Coil Current Waveforms. Energies 2022; 15:1702. [DOI: 10.3390/en15051702] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [What about the content of this article? (0)] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/10/2022]
Abstract
In the field of nuclear fusion, the power exhaust problem is still an open issue and represents one of the biggest problems for the realization of a commercial fusion power plant. According to the “European Fusion Roadmap”, a dedicated facility able to investigate possible solutions to heat exhaust is mandatory. For this purpose, the mission of the Divertor Tokamak Test (DTT) tokamak is the study of different solutions for the divertor. This paper presents the plasma scenarios for standard and alternative configurations in DTT. The Single Null scenario is described in detail. The alternative configurations are also presented, showing the good flexibility of the machine.
Collapse
|