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Fusion energy: Progress, partnerships, and the path to deployment
Over the past decade, fusion energy has moved decisively from scientific aspiration toward a credible pathway to a new energy technology. Thanks to long-term federal support, we have significantly advanced our fundamental understanding of plasma physics—the behavior of the superheated gases at the heart of fusion devices. This knowledge will enable the creation and control of fusion fuel under conditions required for future power plants. Our progress is exemplified by breakthroughs at the National Ignition Facility and the Joint European Torus.
M. Aquilini, L. Baldi, P. Bibet, R. Bozzi, A. Bruschi, R. Cesario, S. Cirant, C. Ferro, F. Gandini, S. di Giovenale, G. Granucci, T. Fortunato, G. Maddaluno, F. de Marco, G. Maffia, A. Marra, V. Mellera, F. Mirizzi, V. Muzzini, A. Nardone, A. Orsini, M. Papalini, P. Papitto, V. Pericoli-Ridolfini, P. Petrolini, S. Petrosino, S. Podda, G. L. Ravera, G. B. Righetti, M. Roccon, F. Santini, M. Sassi, A. Simonetto, C. Sozzi, N. Spinicchia, A. A. Tuccillo, P. Zampelli
Fusion Science and Technology | Volume 45 | Number 3 | May 2004 | Pages 459-482
Technical Paper | Frascati Tokamak Upgrade (FTU) | doi.org/10.13182/FST04-A525
Articles are hosted by Taylor and Francis Online.
High-frequency wave systems with high-power density launching capability have been the preferred choice to heat the Frascati Tokamak Upgrade (FTU) because of physics arguments (electron heating at very high density) and space constraints from the compactness of the machine design (8-cm-wide port). They do include an 8-GHz lower hybrid current drive (LHCD) system, a 140-GHz electron cyclotron resonance heating (ECRH) system, and a 433-MHz ion Bernstein waves system (IBW). The technical aspects of these systems will be reviewed in this article. The main features of the design include the following: (a) a very compact conventional LHCD grill with a compact window to keep the vacuum on 48 (12 columns, 4 rows) individual waveguides allowing the maximum flexibility in spectra generation to be achieved; power handling up to [approximately equal to]10 kW/cm2 has been achieved, (b) ECRH launchers designed as a quasi-optical system (implementing ITER relevant solutions) retaining the maximum flexibility in the equatorial launcher (poloidal/toroidal steerability) to exploit a variety of scenarios, (c) a two-waveguides launching array making the IBW experiment on FTU unique. Other technical aspects (sources, transmission lines, etc.) are also reviewed. The development of a new ITER relevant lower hybrid launcher, the passive active multijunction, is described.