ITER Control System Model: A full-scale simulation platform for the CODAC infrastructure
- 1. IST-IPFN, Av. Rovisco Pais 1, Lisbon 1049-001 (Portugal)
- 2. ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, St. Paul Lez Durance Cedex 13067 (France)
Description
ITER Control System Model (ICM) is a simulation platform for CODAC that is currently being developed at ITER. CODAC is the conventional control system responsible for operating all plant systems from the 35 member states that are contributing to the ITER development. ICM is a full-scale implementation of CODAC that follows all ITER hardware and software conventions, but does not have any signal interfaces to other components of ITER nor any simulation of physical processes. Instead, it relies on state-based simulators that are used to verify CODAC operation at different stages of ITER execution. ICM currently consists of a single server cubicle that houses all hardware and software required to run a full-scale control system configuration without any dependencies on external servers. With its self-sustaining and isolated nature, ICM is capable of simulating the production stage of ITER. It provides an excellent test environment for various CODAC technologies and validating the interoperability of all the different plant systems across the infrastructure, which will contribute to minimizing the downtime of ITER due to avoidable errors. ICM is also being considered as a potential operator training facility.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2018.01.060Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2018.01.060;
- PII
- S0920379618300784;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 128
- Journal Page Range
- p. 86-89
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51012086
- Subject category
- S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- COMPUTER CODES; COMPUTERIZED SIMULATION; CONTROL SYSTEMS; ITER TOKAMAK; SIMULATORS
- Descriptors DEC
- ANALOG SYSTEMS; CLOSED PLASMA DEVICES; FUNCTIONAL MODELS; SIMULATION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Notes
- © 2018 Elsevier B.V. All rights reserved.