Successful demonstration of diagnostics instrumentation
CODAC (Control, Data Access and Communication) is the central, conventional control system responsible for operating the ITER device. It provides the interface "language" for 220 ITER plant instrumentation and control (I&C) systems containing actuators, sensors and all instrumentation and control functions required to measure and control the plasma parameters.
Because plant I&C systems are being procured together with the plant systems from the ITER Members, whereas CODAC is implemented by the ITER Central Team, the interface between the central system and the plant system I&Cs must be well defined and strictly adhered to. A uniform, standardized approach to design of plant system controls is also important to reduce overall project manufacturing and maintenance costs.
In order to facilitate integration, CODAC has organized plant system I&Cs into groups that represent the functional needs of tokamak operation (as illustrated in the image below, levels 1 and 2). Diagnostics represents about 50 percent of all ITER plant I&Cs.
A graph of the ITER Control Breakdown Structure, with diagnostics D1 and D2 on level 2 (yellow) and examples (in green) of the more than 45 individual diagnostic measurement systems at level 3.
Pilot projects have allowed the CODAC team to test plant I&C systems based on the ITER CODAC technology both on the ITER site and in the arenas of operating tokamaks worldwide. In 2012, CODAC successfully demonstrated its capability to control fuelling at the Korean tokamak KSTAR and to operate the flywheel generator control system at the Frascati Tokamak Upgrade (FTU) Project in Italy. In addition, the ITER Steady State Electrical Network (SSEN) powering the ITER facility has been monitored by CODAC since September 2011. In the latest practical demonstration, a prototype of a neutron diagnostics plant I&C system was demonstrated to a large group of diagnosticians in the CODAC control roomâa specially equipped facility located in the basement of ITER Headquarters. The divertor neutron flux monitor, procured through the Russian Domestic Agency, is a diagnostic that measures the fusion power of the ITER Tokamak. In a close association between the ITER CODAC team and Russian colleagues, the idea was born to convert a diagnostic plant I&C example (created with the objective of simplification, cost reduction, standardization and full integration with ITER control system) into a basic plant I&C of a real diagnostic for evaluation by the Russian Domestic Agency.
The control room operator screen for manual operation. The screen is partitioned in sections for configuration, control, status monitoring and measurement of raw and processed data.
The design followed the standard system engineering methodology developed for diagnostics and implemented in compliance with the Plant Control Design Handbook (see insert below), utilizing CODAC Core System and CODAC-provided tools and data repositories. The implementation followed extensive testing documented in detailed reports. Before shipping the plant I&C to Russia, a demonstration was made in manual and automated operation to large group of diagnosticians in the CODAC Control Room.
The demonstration proved that complex, and high performance diagnostics can be built in compliance with the ITER Plant Control Design Handbook, while meeting the stringent requirements of the diagnostics.
The fusion power measurement is based on fission chambers which produce short electrical pulses where the pulse rate is proportional to the fusion power. To cover the wide dynamic range of more the 6 orders of magnitude and a fast measurement update every millisecond, a complex analysis of millions of data samples are required. The demonstration covered not only the aspects of high performance data processing but also the needs for the execution of elaborated procedures such as various types of calibrations, built-in health management, raw data archiving, and finally the fully automated operation that will be supervised by the central CODAC system. This is the first time diagnostic plant I&C is fully based on the CODAC technology, making use of the latest CODAC features.
Plant Control Design Handbook
The ITER Plant Control Design Handbook (PCDH) defines standards, specifications and interfaces applicable to ITER plant system instrumentation and control (I&C). These standards are essential for ITER to:
⢠Integrate all plant systems I&C into one integrated control system
⢠Maintain all plant system I&C after delivery acceptance
⢠Contain cost through economies of scale (spare parts, expertise ...)
The latest PCDH (version 7) issued in February 2013 is the final version to be used to design and manufacture the production I&C systems for ITER. By publishing a full set of PCDH documentation, together with regular releases of the CODAC Core System software, ITER seeks to involve the control system community in the testing and verification of ITER I&C standards in order to arrive at a modern and robust control system suitable for ITER and for scientific installations around the world.
The PCDH consists of a master document and satellite documents. The master document contains principal requirements for ITER plant system I&C; satellite documents go deeper into the details of various I&C subjects providing recommendations, guidelines and examples on how to apply the PCDH. While the core document is fixed, satellite documents may evolve with time to incorporate the latest project developments or manage obsolescence.