Overview of the Preliminary Design of the ITER Plasma Control System [IAEA-CN--234]
- 1. International Thermonuclear Experimental Reactor (ITER), Cadarache Centre, 13108 Saint-Paul-lès-Durance (France)
- 2. Consorzio CREATE, 80125 Napoli (Italy)
- 3. Università degli Studi di Napoli Federico II, 80138 Napoli (Italy)
Description
Full text: The Preliminary Design of the ITER plasma control system (PCS) has been carried out since 2014 by members of the ITER Organization and a number of plasma control experts from CCFE, CEA-Cadarache, CREATE, Efremov, General Atomics, IPP-Garching, and Kurchatov as well as through a collaboration with Eindhoven University of Technology. This work builds on the PCS Conceptual Design that was approved in 2013 and focusses on the needs for 1st plasma and early plasma operation in H/He up to 15 MA operation with moderate auxiliary heating power in L-mode. Initial control schemes for plasma initiation, current rise, vertical stability, plasma position and shape, X-point formation, divertor operation, and density control with gas puffing and pellet injection are being developed. Commissioning of the electron cyclotron, ion cyclotron, and neutral beam heating systems are also included. Support functions for stray field topology and real-time plasma boundary reconstruction are included. In addition, initial event handling schemes for essential plant system faults and for disruption protection are being developed. The PCS architecture must also be capable of handling basic control for early plant system and plasma commissioning and the advanced control functions that will be needed for future high performance operation up to Q = 10 and for long pulse noninductive scenarios. 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 including those of the associated diagnostics and actuators needed to carry out the control functions. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- 26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material
- Imprint Pagination
- 935 p.
- Journal Page Range
- p. 363
- Report number
- IAEA-CN--234
Conference
- Title
- 26. IAEA Fusion Energy Conference
- Acronym
- FEC 2016
- Dates
- 17-22 Oct 2016
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50032078
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTUATORS; CONTROL SYSTEMS; DESIGN; DIVERTORS; ECR HEATING; ENGINEERING; ICR HEATING; ITER TOKAMAK; L-MODE PLASMA CONFINEMENT; NEUTRAL PARTICLES; PARTICLE BEAMS; PELLET INJECTION; PLASMA; PULSES; SAFETY; SIMULATORS; STABILITY
- Descriptors DEC
- ANALOG SYSTEMS; BEAMS; CLOSED PLASMA DEVICES; CONFINEMENT; FUNCTIONAL MODELS; HEATING; HIGH-FREQUENCY HEATING; MAGNETIC CONFINEMENT; PLASMA CONFINEMENT; PLASMA HEATING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Notes
- Abstract only; This record replaces 49093241
- Secondary number(s)
- IAEA-CN--234-0348