From the conceptual design to the first simulation of the new WEST plasma control system

Nouailletas, R.; Ravenel, N.; Signoret, J.; Treutterer, W.; Spring, A.; Lewerentz, M.; Rapson, C.; Masand, H.; Dhongde, J.; Moreau, Philippe; Guillerminet, B.; Brémond, S.; Allegretti, L.; Raupp, G.; Werner, A.; Laurent, François; Nardon, E.; Bhandarkar, M.

doi:10.1016/j.fusengdes.2015.05.023

Cited by 9 publications

(2 citation statements)

References 8 publications

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“…Some of the advanced control features required of the ITER PCS have been implemented to some extent on existing devices, including real-time actuator management [26,27] and exception handling [28][29][30]. The limited set of actuators, particularly the auxiliary heating systems, must perform multiple control functions throughout a plasma discharge sequentially or simultaneously as events occur in the plasma or plant systems.…”

Section: Actuator Management and Exception Handlingmentioning

confidence: 99%

Overview of the preliminary design of the ITER plasma control system

et al. 2017

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An overview of the preliminary design of the ITER plasma control system (PCS) is described here, which focusses on the needs for 1st plasma and early plasma operation in hydrogen/ helium (H/He) up to a plasma current of 15 MA with moderate auxiliary heating power in low confinement mode (L-mode). Candidate control schemes for basic magnetic control, including divertor operation and kinetic control of the electron density with gas puffing and pellet injection, were developed. Commissioning of the auxiliary heating systems is included as well as support functions for stray field topology and real-time plasma boundary reconstruction. Initial exception handling schemes for faults of essential plant systems and for disruption protection were developed. The PCS architecture was also developed to be capable of handling basic control for early commissioning and the advanced control functions that will be needed for future high performance operation. A plasma control simulator is also being developed to test and validate control schemes. To handle the complexity of the ITER PCS, a systems engineering approach has been adopted with the development of a plasma control database to keep track of all control requirements.

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Section: Actuator Management and Exception Handlingmentioning

confidence: 99%

Overview of the preliminary design of the ITER plasma control system

et al. 2017

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“…Recently, the control system framework of the ASDEX Upgrade (AUG) experiment, DCS [3], was adopted as a base control system of the WEST project [4] and moved from a dedicated implementation to a general-purpose platform. From its beginning DCS had been built on the above-mentioned principles for portable design.…”

Section: Introductionmentioning

confidence: 99%

Transforming the ASDEX Upgrade discharge control system to a general-purpose plasma control platform

Treutterer

Cole

Gräter

et al. 2015

Fusion Engineering and Design

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The ASDEX Upgrade Discharge Control System DCS is a modern and mature product, originally designed to regulate and supervise ASDEX Upgrade Tokamak plasma operation. In its core DCS is based on a generic, versatile real-time software framework with a plugin architecture that allows to easily combine, modify and extend control function modules in order to tailor the system to required features and let it continuously evolve with the progress of an experimental fusion device. Due to these properties other fusion experiments like the WEST project have expressed interest in adopting DCS.For this purpose, essential parts of DCS must be unpinned from the ASDEX Upgrade environment by exposure or introduction of generalised interfaces. Re-organisation of DCS modules allows distinguishing between intrinsic framework core functions and device-specific applications. In particular, DCS must be prepared for deployment in different system environments with their own realisations for user interface, pulse schedule preparation, parameter server, time and event distribution, diagnostic and actuator systems, network communication and data archiving.The article explains the principles of the revised DCS structure, derives the necessary interface definitions and describes major steps to achieve the separation between general-purpose framework and fusion device specific components.

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Advancements in Plasma Control Supervision

Meyer

Padayachee

2018

J Fusion Energ

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From the conceptual design to the first simulation of the new WEST plasma control system

Cited by 9 publications

References 8 publications

Overview of the preliminary design of the ITER plasma control system

Overview of the preliminary design of the ITER plasma control system

Transforming the ASDEX Upgrade discharge control system to a general-purpose plasma control platform

Advancements in Plasma Control Supervision

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