The magnetics diagnostic set for ITER

Chavan, R.; Chitarin, G.; Delogu, R.; Encheva, A.; Gallo, Antonio; Hodgson, E.R.; Ingesson, L. C.; Le-Luyer, A.; Lister, J.B.; Moreau, Ph.; Moret, J.M.; Peruzzo, S.; Romero, Jesús; Testa, D.; Toussaint, M.; Vayakis, G.; Vila, R.

doi:10.1016/j.fusengdes.2008.12.103

Cited by 13 publications

(2 citation statements)

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“…For ITER, the control loop cycle for vertical stabilization will likely be less demanding ( ms). However, the amount of magnetic signals that may be required to be processed simultaneously will be significantly higher (up to 800 signals from the different magnetic diagnostics [44]) and their measurements may have to be integrated with the measurements from the microwave plasma positioning reflectometer [45] for cross-calibration. Higher reliability is also expected as vertical stabilization loss should be avoided.…”

Section: Developing Atca Systems For Fusion Experimentsmentioning

confidence: 99%

ATCA Advanced Control and Data Acquisition Systems for Fusion Experiments

Gonçalves¹,

Sousa²,

Batista³

et al. 2010

IEEE Trans. Nucl. Sci.

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The next generation of large-scale physics experiments will be highly complex, raise new challenges in the field of control and automation systems and demand well integrated, interoperable set of tools with a high degree of automation. Fusion experiments will face similar needs and challenges. In nuclear fusion activities, e.g., JET and other devices, the demand has been to develop front-end electronics with large output bandwidth and data processing Multiple-Input-Multiple-Output (MIMO) controllers with efficient resource sharing between control tasks on the same unit and massive parallel computing capabilities. Future systems, such as ITER, are envisioned to be more than an order of magnitude larger than those of today. Fast control plant systems based on embedded technology with higher sampling rates and more stringent real-time requirements (feedback loops with sampling rates > 1 kHz) will be demanded. Furthermore, in ITER, it is essential to ensure that control loss is a very unlikely event and more challenging will be providing robust, fault tolerant, reliable, maintainable, secure and operable control systems. ATCA (Advanced Telecommunications Computing Architecture) is the most promising architecture to substantially enhance the performance and capability of existing standard systems delivering high throughput as well as high availability. Leveraging on ongoing activities at European fusion facilities, e.g., JET and COMPASS, this contribution will detail the control and data acquisition needs and challenges of the fusion community, justify the option for ATCA and, in the process, build the case for establishing ATCA as an instrumentation standard.

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Section: Developing Atca Systems For Fusion Experimentsmentioning

confidence: 99%

ATCA Advanced Control and Data Acquisition Systems for Fusion Experiments

Gonçalves¹,

Sousa²,

Batista³

et al. 2010

IEEE Trans. Nucl. Sci.

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“…Coils can be shielded, but then their dynamic response becomes slow. Magnetic diagnostics are also subject to drift, so will need correcting over long pulses [4]. Developing accurate and reliable diagnostics is extremely important since position control actuators in DEMO are challenged even in simulations with ideal diagnostics [5] and loss of control would lead to a disruption, which must be avoided at all costs.…”

Section: Introductionmentioning

confidence: 99%

Proof of principle of electron cyclotron emission as a complementary diagnostic for the plasma position

Rapson

Denk

Fischer

et al. 2016

2016 41st International Conference on Infrared, Millimeter, and Terahertz Waves (IRMMW-THz)

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Today's tokamaks use magnetic diagnostics to control the plasma position. In future fusion reactors (e.g. DEMO) the performance of magnetic diagnostics will be compromised by integrator drifts over long pulses and by radiation. Microwave diagnostics are good alternatives, as they are expected to be robust to the harsh radiation environment. Reflectometry has shown its potential to measure the density profile and hence to derive the separatrix position. This submission demonstrates how Electron Cyclotron Emission (ECE) can do the same via the electron temperature (Te) profile. It will be shown that Te at the separatrix can be calculated as a function of several well-diagnosed plasma parameters for a wide range of scenarios. From ECE measurements, the Te profile can be derived, taking into account problematic effects such as shinethrough and corrupt measurement channels. Trivially, finding the position where the profile matches the separatrix temperature gives the separatrix position. In a proof-of-principle experiment on ASDEX Upgrade, the radial plasma position was controlled using the separatrix position derived from ECE measurements. After initial success, problems with cutoff and latency led to a loss of control. An outline is given on how to remedy these issues and develop this proop-of-principle into a viable diagnostic for fusion reactors.

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