Requirements specification for the Neutral Beam Injector on FAST

Baruzzo, M.; Bolzonella, T.; Calabrò, G.; Crisanti, F.; Cucchiaro, A.; Marcuzzi, D.; Rigato, W.; Schneider, M.; Sonato, P.; Valisa, M.; Zaccaria, P.; Artaud, Jean-François; Basiuk, V.; Cardinali, A.; Imbeaux, F.; Taroni, L. Lauro; Marinucci, M.; Mantica, P.; Zonca, F.

doi:10.1016/j.fusengdes.2011.03.012

Cited by 3 publications

(4 citation statements)

References 6 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The flexibility of FAST ICRH system (see [14] and section 4) gives us the confidence that FAST can indeed address cross-scale couplings of micro-turbulence with meso-scale fluctuations with varying choices of the ICRH resonant layer. In FAST, the flexibility in controlling the radial FP power density profile that is an important knob for investigating linear and nonlinear physics is also ensured by the possibility of accommodating up to 10 MW of NNBI [12,14,38]. The details of the NNBI systems, and the complete scenarios flexibility, are out of the scope of this paper and are going to be presented in a dedicated paper [38].…”

Section: Fast Scientific Rationale and Plasma Physics Scenariosmentioning

confidence: 99%

“…In FAST, the flexibility in controlling the radial FP power density profile that is an important knob for investigating linear and nonlinear physics is also ensured by the possibility of accommodating up to 10 MW of NNBI [12,14,38]. The details of the NNBI systems, and the complete scenarios flexibility, are out of the scope of this paper and are going to be presented in a dedicated paper [38]. However, just to address the system capabilities and the enhanced flexibility of the machine, in figures 4(a) and (b) we report the fast ions perpendicular and parallel beta profiles (solid lines), normalized to the ITER β H,max (=1.1%): on the same frames we also show (dashed lines) the radial profiles of α H = −Rq 2 (dβ H /dr), normalized to (R/a)q 2 β H,max .…”

Section: Fast Scientific Rationale and Plasma Physics Scenariosmentioning

confidence: 99%

See 1 more Smart Citation

The Fusion Advanced Studies Torus (FAST): a proposal for an ITER satellite facility in support of the development of fusion energy

Pizzuto¹,

Gnesotto²,

Lontano³

et al. 2010

Nucl. Fusion

Self Cite

View full text Add to dashboard Cite

FAST is a new machine proposed to support ITER experimental exploitation as well as to anticipate DEMO relevant physics and technology. FAST is aimed at studying, under burning plasma relevant conditions, fast particle (FP) physics, plasma operations and plasma wall interaction in an integrated way. FAST has the capability to approach all the ITER scenarios significantly closer than the present day experiments using deuterium plasmas. The necessity of achieving ITER relevant performance with a moderate cost has led to conceiving a compact tokamak (R = 1.82 m, a = 0.64 m) with high toroidal field (B T up to 8.5 T) and plasma current (I p up to 8 MA). In order to study FP behaviours under conditions similar to those of ITER, the project has been provided with a dominant ion cyclotron resonance heating system (ICRH; 30 MW on the plasma). Moreover, the experiment foresees the use of 6 MW of lower hybrid (LHCD), essentially for plasma control and for non-inductive current drive, and of electron cyclotron resonance heating (ECRH, 4 MW) for localized electron heating and plasma control. The ports have been designed to accommodate up to 10 MW of negative neutral beams (NNBI) in the energy range 0.5-1 MeV. The total power input will be in the 30-40 MW range under different plasma scenarios with a wall power load comparable to that of ITER (P /R ∼ 22 MW m −1). All the ITER scenarios will be studied: from the reference H mode, with plasma edge and ELMs characteristics similar to the ITER ones (Q up to ≈1.5), to a full current drive scenario, lasting around 170 s. The first wall (FW) as well as the divertor plates will be of tungsten in order to ensure reactor relevant

show abstract

Section: Fast Scientific Rationale and Plasma Physics Scenariosmentioning

confidence: 99%

Section: Fast Scientific Rationale and Plasma Physics Scenariosmentioning

confidence: 99%

The Fusion Advanced Studies Torus (FAST): a proposal for an ITER satellite facility in support of the development of fusion energy

Pizzuto¹,

Gnesotto²,

Lontano³

et al. 2010

Nucl. Fusion

Self Cite

View full text Add to dashboard Cite

show abstract

“…Special machine ports were designed to accommodate a 10 MW (45° inclined on the plasma cord) Negative Neutral Beam Injection (NNBI) system [16].…”

Section: Vacuum Vesselmentioning

confidence: 99%

Advances in the FAST program

Cucchiaro

Brolatti

Calabrò

et al. 2011

2011 IEEE/NPSS 24th Symposium on Fusion Engineering

Self Cite

View full text Add to dashboard Cite

FAST (Fusion Advanced Studies Torus) is a p ro p osal for a Satellite Facility which can contribute the ra p id ex p loitation of ITER and p re p are ITER and DEMO regimes of o p eration, as well as ex p loiting innovative DEMO technology. FAST o p erates with high p erformance H-Mode (BT up to 8.5 T; Ip up to 8 MA) as well as Advanced Tokamak o p eration (Ip=3 MA), and full non inductive current scenario (Ip=2 MA) [1). The p roject is based on a dominant 30 MW of ICRH, 6 MW of LH and 4 MW of ECRH. Helium gas at 30K is used for cooling the resistive co pp er magnets, which dimensions have been determined to limit the coil tem p erature at the end of the longest p ulses ( p ulse length u p to 170 s). The p eak current density in the reference H-mode is about 45 MA/m 2 • The Finite Element Method (FEM) has been em p loyed to analyse the stresses of the load assembly structure (2) using the ANSYS code. Due to the full structural coo p eration, the Toroidal Field Coils, Central Solenoid and mechanical structure, have been modelled as a whole, using mechanical and thermal smeared p ro p erties. Structural analyses were p erformed at the most significant times of the o p erating scenario. The FW consists of a bundle of coaxial tubes armoured with 4

show abstract

“…1). The vacuum vessel will be in Inconel, with ports in stainless steel, and it is designed with a very large number of ports that include the possibility to accommodate up to 20 MW (on two different ports) of tangential (∼45 • on the magnetic axis) NNBI at 0.7-1.0 MeV [11]. In Fig.…”

Section: Introductionmentioning

confidence: 99%