Chapter 1: The FTU Program

Gormezano, C.; Marco, F. De; Mazzitelli, G.; Pizzuto, A.; Righetti, Giulia; Romanelli, Francesco

doi:10.13182/fst04-a515

Cited by 47 publications

(49 citation statements)

References 9 publications

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“…It is a compact Tokamak with high magnetic field (up to 8 T) and plasma current up to 1.6 MA [8]. The stainless steel liner is covered internally, by a toroidal limiter made by 2 cm thick tiles of molybdenum.…”

Section: Introductionmentioning

confidence: 99%

Peaked density profiles and MHD activity on FTU in lithium dominated discharges

Tudisco

Mazzotta

Botrugno

et al. 2010

Fusion Engineering and Design

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Section: Introductionmentioning

confidence: 99%

Peaked density profiles and MHD activity on FTU in lithium dominated discharges

Tudisco

Mazzotta

Botrugno

et al. 2010

Fusion Engineering and Design

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“…A new Real-Time (RT) data acquisition and elaboration system is being implemented in FTU tokamak (major radius R=0.935 m, minor radius, a=0.31 m, max toroidal field 8 T, max plasma current 1.6 MA, typical flat top pulse duration 1.5 s) [1] to perform experiments of RT control of magnetohydrodinamic activity through a newly installed fast steerable two beams EC launcher [2]. The main goal of the system is the detection and control of m/n = 3/2 and 2/1 (neoclassical) tearing modes, (N)TM, and the control of the period of sawteeth activity in order to prevent the seeding of NTMs.…”

Section: Introductionmentioning

confidence: 99%

The Real-Time system for MHD activity control in the FTU tokamak

Sozzi

Alessi

Boncagni

et al. 2012

EPJ Web of Conferences

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Abstract. The Real-Time system for the control of the magnetohydrodynamics instabilities in FTU tokamak is presented. It is based on both a-priori information derived from statistical treatment of a database and Real-Time elaboration of live diagnostics data. The analysis codes are executed in different time threads based on multi-processors machines. The actuator is the 2x0.4MW 140 GHz ECRH system equipped with the new fast quasi-optical steerable launcher.

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“…The FTU distinctive location [5,6] in this panorama dwells in the possibility to deal with two major problems of ITBs in an ITER-like reactor at the same time. These are the high density, that has to be close ton e ≈ 10 20 m −3 [1] to have a high fusion yield, and the by far dominant electron (e − ) heating (from α-particles) with negligible momentum input from external sources.…”

Section: Introductionmentioning

confidence: 99%

“…Conversely FTU cannot deal with some questions such as stability at high β, due to its high magnetic field, the role of fast particles and the divertor physics, FTU being a limiter device. Further details on the FTU device can be found in [5].…”

Section: Introductionmentioning

confidence: 99%

High density internal transport barriers for burning plasma operation

Ridolfini¹,

Barbato²,

Buratti³

et al. 2005

Plasma Phys. Control. Fusion

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A tokamak plasma with internal transport barriers (ITBs) is the best candidate for a steady ITER operation, since the high energy confinement allows working at plasma currents (I p ) lower than the reference scenario. To build and sustain an ITB at the ITER high density ( 10 20 m −3 ) and largely dominant electron (e − ) heating is not trivial in most existing tokamaks. FTU can instead meet both requests, thanks to its radiofrequency heating systems, lower hybrid (LH, up to 1.9 MW) and electron cyclotron (EC up to 1.2 MW). By the combined use of them, ITBs are obtained up to peak densities n e0 > 1.3 × 10 20 m −3 , with central e − temperatures T e0 ≈ 5.5 keV, and are sustained for as long as the heating pulse is applied (>35 confinement times, τ E ). At n e0 ≈ 0.8 × 10 20 m −3 T e0 can be larger than 11 keV. Almost full current drive (CD) and an overall good steadiness is attained within about one τ E , 20 times faster than the ohmic current relaxation time. The ITB extends over a central region with an almost flat or slightly reversed q profile and q min ≈ 1.3 that is fully sustained by off-axis lower hybrid current drive. Consequent to this is the beneficial good alignment of the bootstrap current, generated by the ITB large pressure gradients, with the LH driven current. Reflectometry shows a clear change in the turbulence 0741-3335/05/SB0285+17$30.00 © 2005 IOP Publishing Ltd Printed in the UK B285 B286 V Pericoli Ridolfini et al

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Chapter 1: The FTU Program

Cited by 47 publications

References 9 publications

Peaked density profiles and MHD activity on FTU in lithium dominated discharges

Peaked density profiles and MHD activity on FTU in lithium dominated discharges

The Real-Time system for MHD activity control in the FTU tokamak

High density internal transport barriers for burning plasma operation

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