Published October 2010 | Version v1
Report

Plasma Models for Real-Time Control of Advanced Tokamak Scenarios

  • 1. CEA, IRFM, 13108 Saint-Paul-lez-Durance (France)
  • 2. General Atomics, San Diego, CA 92186 (United States)
  • 3. Lehigh University, Bethlehem, PA 18015 (United States)
  • 4. University of Tokyo, 277-8561, Kashiwa (Japan)
  • 5. Japan Atomic Energy Agency, Naka, Ibaraki 311-0193 (Japan)

Description

Full text: An integrated plasma profile control strategy, ARTAEMIS, is being developed for extrapolating present-day advanced tokamak (AT) scenarios to steady state operation. The approach is based on semi-empirical modeling. It was initially explored on JET, for current profile control only. The present paper deals with the generalization of this strategy to simultaneous magnetic and kinetic control. The methodology is generic and can be applied to any device, with different sets of heating and current drive actuators, controlled variables and profiles. In AT discharges, the multiple parameter profiles which define the plasma state (safety factor, plasma rotation and pressure, etc...) are known to be strongly coupled, and a limited number of heating and current drive (HCD) actuators are available for plasma control. The system identification algorithms take advantage of the large ratio between the magnetic and thermal diffusion time scales and have been recently applied, in their full version, on both JT-60U and DIII-D data. On JT-60U, an existing series of high-bootstrap-current (70%), 0.9 MA non-inductive AT discharges were used. The actuators consisted of four groups of neutral beam injectors corresponding to on-axis perpendicular NBI, off-axis perpendicular NBI, on-axis co-current tangential NBI and off-axis co-current tangential NBI. On DIII-D, actuator modulation experiments were carried out in the loop voltage control mode to avoid feedback in the response data from the primary circuit. The plasma current varied between 0.7 and 1.2 MA. In addition to the loop voltage, the four HCD actuators were co-current, counter-current and balanced NBI, and electron cyclotron current drive. The reference plasma state was that of an AT scenario which had been optimized to combine non-inductive current fractions near unity with 3.5 <βN < 3.9, bootstrap current fractions of > 65%, and H98(y,2) =1.5. The determination of the device-specific, control-oriented models that are needed to compute optimal controller matrices is discussed. The response of the relevant parameter profiles to variations of specific actuators can be satisfactorily identified from a small set of dedicated experiments. This provides, for control purposes, a readily available alternative to first-principle plasma modeling. (author)

Part of:
23. IAEA Fusion Energy Conference. Book of Abstracts

Additional details

Publishing Information

Imprint Title
23. IAEA Fusion Energy Conference. Book of Abstracts
Imprint Pagination
637 p.
Journal Page Range
p. 224
Report number
IAEA-CN--180

Conference

Title
23. IAEA Fusion Energy Conference
Acronym
FEC 2010
Dates
11-16 Oct 2010
Place
Daejeon (Korea, Republic of)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
43040925
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACTUATORS; ALGORITHMS; BOOTSTRAP CURRENT; CONTROL; COUNTER CURRENT; DOUBLET-3 DEVICE; ECR CURRENT DRIVE; ELECTRIC POTENTIAL; FEEDBACK; JT-60U TOKAMAK; PLASMA; PLASMA HEATING; PLASMA RADIAL PROFILES; PLASMA SIMULATION; STEADY-STATE CONDITIONS; THERMAL DIFFUSION
Descriptors DEC
CLOSED PLASMA DEVICES; CURRENTS; DIFFUSION; ELECTRIC CURRENTS; HEATING; MATHEMATICAL LOGIC; NON-INDUCTIVE CURRENT DRIVE; SIMULATION; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

Notes
1 ref
Collaborations
ITPA-IOS Group Members and Experts
Secondary number(s)
EXW--P2-07