The ITER CODAC conceptual design

Lister, J.B.; Farthing, J.; Greenwald, M.; Yonekawa, I.

doi:10.1016/j.fusengdes.2007.01.013

Cited by 42 publications

(12 citation statements)

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“…This section focuses on the review on data acquisition and electronic hardening progresses reported in ANIMMA conferences. The next generation of large-scale physics experiments, nuclear instrumentation and application will be highly complex, raises new challenges in the field of control and automation systems and demands well integrated, interoperable set of tools with a high degree of automation [226][227][228] and HA [229]. New projects prominently feature solutions adopted from other laboratories [230], hardware and software standards and industrial solutions [231].…”

Section: Cross-fertilization Between Disciplinesmentioning

confidence: 99%

Nuclear instrumentation and measurement: a review based on the ANIMMA conferences

Giot

Vermeeren

Lyoussi

et al. 2017

EPJ Nuclear Sci. Technol.

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Abstract. The ANIMMA conferences offer a unique opportunity to discover research carried out in all fields of nuclear measurements and instrumentation with applications extending from fundamental physics to fission and fusion reactors, medical imaging, environmental protection and homeland security. After four successful editions of the Conference, it was decided to prepare a review based to a large extent but not exclusively on the papers presented during the first four editions of the conference. This review is organized according to the measurement methodologies: neutronic, photonic, thermal, acoustic and optical measurements, as well as medical imaging and specific challenges linked to data acquisition and electronic hardening. The paper describes the main challenges justifying research in these different areas, and summarizes the recent progress reported. It offers researchers and engineers a way to quickly and efficiently access knowledge in highly specialized areas.

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Section: Cross-fertilization Between Disciplinesmentioning

confidence: 99%

Nuclear instrumentation and measurement: a review based on the ANIMMA conferences

Giot

Vermeeren

Lyoussi

et al. 2017

EPJ Nuclear Sci. Technol.

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“…1. The MRC processes control functions, handles alarm events, retrieves error logs, and is to be managed as the interface to the CODAC [7]. The MRC communicates with CCR to dispatch control parameters and get back real-time plant data from the LCC.…”

Section: Pf Converter Control Systemmentioning

confidence: 99%

A Timed-Token Based Network for the ITER Poloidal Field Converter Control System

Shen

Gao

et al. 2014

J Fusion Energ

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The control system for poloidal field (PF) in ITER is running in a cluster of distributed controller nodes connected by a soft real-time network. The non-functional performance of network communication, such as latency and jitter, plays an important role in the control system. We analyze the essential of network communication for PF converter control system with stringent real-time requirement and identify the feasibility of the conventional time division method at the request of current data size. However, in order to meet the increased demand for communication data size, we present the design of a timed-token based method and its network scheduler. A test scenario involving a cluster of local control cubicles has been set up to verify the method. The test result shows the timed-token method is more competent to the conventional method and more qualify to the networked control system of PF converter. Meanwhile, in other network with similar architecture, implementation of the timed-token method can guarantee real-time performance as well.

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“…Thus CODAC will consist of user-workstations to edit and launch schedules, "engines" to execute the "plugins", and communications networks for both supervisory control & status and for process input & output. The CODAC has the several layers in its hardware configuration as shown in Fig.9 [34].…”

Section: Iter and Its Present Statusmentioning

confidence: 99%

Plasma control systems relevant to ITER and fusion power plants

Kurihara¹,

Lister²,

Humphreys³

et al. 2008

Fusion Engineering and Design

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As a complement to ITER, the existing large and medium-size tokamaks are expected to explore more advanced operation scenarios compatible with a future power reactor. Specifically, the following urgent issues are required to be solved hopefully with an experimental demonstration: to work out one or more solutions to maintain a steady-state plasma with high performance (high beta and high bootstrap current fraction), and to suppress plasma instabilities almost completely. The developed solutions have to be confirmed using a DT burning plasma in ITER. In this article, we first review on system configurations and essential functions used for plasma control systems in existing tokamaks, from the viewpoint of technical inheritance of both hardware and software. Second, we discuss what plasma control system is relevant to ITER and fusion power plants from the two viewpoints: operation supervisor and plasma control tool. Finally, we will provide the current design of the ITER plasma control system.

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The ITER CODAC conceptual design

Cited by 42 publications

References 0 publications

Nuclear instrumentation and measurement: a review based on the ANIMMA conferences

Nuclear instrumentation and measurement: a review based on the ANIMMA conferences

A Timed-Token Based Network for the ITER Poloidal Field Converter Control System

Plasma control systems relevant to ITER and fusion power plants

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