Real time magnetic field and flux measurements for tokamak control using a multi-core PCI Express system

Giannone, L.; Schneider, W.; McCarthy, Patrick J.; Sips, A. C. C.; Treutterer, W.; Behler, K.; Eich, T.; Fuchs, Julien; Hicks, N.; Kallenbach, A.; Maraschek, M.; Mlynek, A.; Neu, G.; Pautasso, G.; Raupp, G.; Reich, M.; Schuhbeck, K. H.; Stöber, J.; Volpe, F.; Zehetbauer, T.; Cerna, M.; Debelle, T.; Marker, B.; McCaslin, S.; Munroe, M.; Wenzel, L.

doi:10.1016/j.fusengdes.2008.12.059

Cited by 15 publications

(10 citation statements)

References 16 publications

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“…For a proper mapping of the measurements from the ECE a reliable and well defined equilibrium is needed (for example in [59]) Ideally this would be based on a direct current density measurement. The Motional Stark Effect (MSE) measurement at least provides directly measured pitch angles of the local magnetic field (for example in [60]), which helps to constrain the equilibrium reconstruction.…”

Section: Relevant Measurements For Detecting Ntmsmentioning

confidence: 99%

Control of neoclassical tearing modes

Maraschek

2012

Nucl. Fusion

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Abstract. Neoclassically driven tearing modes (NTM) are a major problem for tokamaks operating in a conventional ELMy H-mode scenario. Depending on the mode numbers these pressure driven perturbations cause a mild reduction of the maximum achievable β N = β t /() before the onset of the NTM, or can even lead to disruptions at low edge safety factor, q 95 . A control of this type of modes in high β N plasmas is therefore of vital interest for magnetically confined fusion plasmas. The control consists of two major approaches, namely the control of the excitation of these modes and the removal, or at least mitigation, of these modes, once an excitation could not be avoided. For both routes examples will be given and the applicability of these approaches to ITER will be discussed.

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Section: Relevant Measurements For Detecting Ntmsmentioning

confidence: 99%

Control of neoclassical tearing modes

Maraschek

2012

Nucl. Fusion

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“…These diagnostics operate from separate systems on a common shared memory from which and in which they read and place their data. Major components are an equilibrium solver [17], density profile from interferometry [18], ray-tracing for all ECRH-beams and a correlation analysis of the 60 new fast ECE channels with the n=2 component (for (3,2)-NTMs) or the n=1, m=2 component of the Mirnov-signals [15]. Figure 1 summarizes the level reached so far: the ECEMirnov correlation allows reliably to localize a (3,2)-NTM.…”

Section: Ntmsmentioning

confidence: 99%

ECRH on ASDEX Upgrade - System Status, Feed-Back Control, Plasma Physics Results -

Stober

Bock

Höhnle

et al. 2012

EPJ Web of Conferences

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Abstract. The ASDEX Upgrade (AUG) ECRH system now delivers a total of 3.9 MW to the plasma at 140 GHz. Three new units are capable of 2-frequency operation and may heat the plasma alternatively with 2.1 MW at 105 GHz. The system is routinely used with X2, O2, and X3 schemes. For B t = 3.2 T also an ITER-like O1-scheme can be run using 105 GHz. The new launchers are capable of fast poloidal movements necessary for real-time control of the location of power deposition. Here real-time control of NTMs is summarized, which requires a fast analysis of massive data streams (ECE and Mirnov correlation) and extensive calculations (equilibria, ray-tracing). These were implemented at AUG using a modular concept of standardized real-time diagnostics. The new realtime capabilities have also been used during O2 heating to keep the first reflection of the non-absorbed beam fraction on the holographic reflector tile which ensures a well defined second pass of the beam through the central plasma. Sensors for the beam position are fast thermocouples at the edge of the reflector tile. The enhanced ECRH power was used for several physics studies related to the unique feature of pure electron heating without fueling and without momentum input. As an example the effect of the variation of the heating mix in moderately heated H-modes is demonstrated using the three available heating systems, i.e. ECRH, ICRH and NBI. Keeping the total input power constant, strong effects are seen on the rotation, but none on the pedestal parameters. Also global quantities as the stored energy are hardly modified. Still it is found that the central ion temperature drops as the ECRH fraction exceeds a certain threshold.

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“…This data set is sampled simultaneously with 10 kHz for the duration of the 10 s discharge using 16 PXI 6143 data acquisition cards mounted in an 18 slot PXI 1045 chassis and connected via a PXI-PCIe 8361 bridge to a PCIe LabVIEW RT 8.6 system with two Intel Xeon 3.0 GHz quad core processors [10]. It was shown that the magnetic probe and flux loop measurement prior to a discharge could be monitored for sensor or integrator failure in real time.…”

Section: Magnetic Equilibriummentioning

confidence: 99%

Data acquisition and real-time signal processing of plasma diagnostics on ASDEX Upgrade using LabVIEW RT

Giannone¹,

Cerna²,

Cole³

et al. 2010

Fusion Engineering and Design

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The existing VxWorks real time system for the position and shape control in ASDEX Upgrade has been extended to calculate magnetic flux surfaces in real time using a multi-core PCI Express system running LabVIEW RT 8.6. Real time signal processing of bolometers and manometers is performed with the on-board FPGA to calculate the measured radiated power flux and particle flux respectively from the raw data. Radiation feedback experiments use halo current measurements from the outer divertor with real time median filter pre-processing to remove the excursions produced by ELM's. Integration of these plasma diagnostics into the control system by the exchange of XML sheets for communicating the real time variables to be produced and consumed is in operation. Reflective memory and UDP are employed by the LabVIEW RT plasma diagnostics to communicate with the control system and other plasma diagnostics in a multi-platform real time network.

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Real time magnetic field and flux measurements for tokamak control using a multi-core PCI Express system

Cited by 15 publications

References 16 publications

Control of neoclassical tearing modes

Control of neoclassical tearing modes

ECRH on ASDEX Upgrade - System Status, Feed-Back Control, Plasma Physics Results -

Data acquisition and real-time signal processing of plasma diagnostics on ASDEX Upgrade using LabVIEW RT

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