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The Resistive Wall Mode Feedback Control System on DIII-D.

The Resistive Wall Mode Feedback Control System on DIII-D. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 7

Book Description
One of the primary instabilities limiting the performance of the plasma in advanced tokamak operating regimes is the resistive wall mode (RWM) [1]. The most common RWM seen in the DIII-D tokamak is originated by an n=1 ideal external kink mode which, in the presence of a resistive wall, is converted to a slowly growing RWM. The mode causes a reduction in plasma rotation, a loss of stored energy, and sometimes leads to plasma disruption. It routinely limits the performance of a tokamak operating near reactor relevant parameter levels. A system designed to actively control the RWM has recently been installed on the DIII-D tokamak for the control of low m n=1 modes. In initial experiments, the control system has been capable of delaying the onset of RWMs in energetic discharges for several hundred milliseconds. The feedback control system consists of detector coils connected via control software to high power current amplifiers driving the excitation coils. The three pairs of excitation coils are each driven by a current amplifier and a DC power supply. The control signal is derived from a set of six sensor coils that measure radial flux as low as one Gauss. The signals are digitally processed by realtime software in the DIII-D Plasma Control System (PCS) to create a command that is sent to the current amplifier, with a cycle time of approximately 100 [mu]s. The amplifiers, designed and fabricated by Robicon Corporation to a specification developed by PPPL and GA, are bipolar devices capable of ±5 kA at 300 V, with an operating bandwidth of approximately 800 Hz ( -3 dB).

The Resistive Wall Mode Feedback Control System on DIII-D.

The Resistive Wall Mode Feedback Control System on DIII-D. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 7

Book Description
One of the primary instabilities limiting the performance of the plasma in advanced tokamak operating regimes is the resistive wall mode (RWM) [1]. The most common RWM seen in the DIII-D tokamak is originated by an n=1 ideal external kink mode which, in the presence of a resistive wall, is converted to a slowly growing RWM. The mode causes a reduction in plasma rotation, a loss of stored energy, and sometimes leads to plasma disruption. It routinely limits the performance of a tokamak operating near reactor relevant parameter levels. A system designed to actively control the RWM has recently been installed on the DIII-D tokamak for the control of low m n=1 modes. In initial experiments, the control system has been capable of delaying the onset of RWMs in energetic discharges for several hundred milliseconds. The feedback control system consists of detector coils connected via control software to high power current amplifiers driving the excitation coils. The three pairs of excitation coils are each driven by a current amplifier and a DC power supply. The control signal is derived from a set of six sensor coils that measure radial flux as low as one Gauss. The signals are digitally processed by realtime software in the DIII-D Plasma Control System (PCS) to create a command that is sent to the current amplifier, with a cycle time of approximately 100 [mu]s. The amplifiers, designed and fabricated by Robicon Corporation to a specification developed by PPPL and GA, are bipolar devices capable of ±5 kA at 300 V, with an operating bandwidth of approximately 800 Hz ( -3 dB).

The Resistive Wall Mode Feedback Stabilization Experiment on DIII-D.

The Resistive Wall Mode Feedback Stabilization Experiment on DIII-D. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
The feedback stabilization of the Resistive Wall Mode (RWM) has begun in the DIII-D Tokamak. The main objective of the experiment is to stabilize the RWM by effecting a ''perfectly'' conducting shell through active compensation of the n= 1 flux leaking through the resistive vacuum vessel. The preliminary results indicate that the n= 1 flux leakage from the vacuum vessel can indeed be compensated by the feedback system, and the amplitude of the magnetohydrodynamic mode can be reduced and the discharge's duration prolonged with a judicious choice of feedback parameters. We briefly describe the initial experimental results and also summarize a new feedback simulation code in toroidal geometry, which should prove useful for better understanding of the RWM feedback process.

Active Feedback Stabilization of the Resistive Wall Mode on the DIII-D Device

Active Feedback Stabilization of the Resistive Wall Mode on the DIII-D Device PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 33

Book Description
A proof of principle magnetic feedback stabilization experiment has been carried out to suppress the resistive wall mode (RWM), a branch of the ideal magnetohydrodynamic (MHD) kink mode under the influence of a stabilizing resistive wall, on the DIII-D tokamak device. The RWM was successfully suppressed and the high beta duration above the no wall limit was extended to more than 50 times the resistive wall flux diffusion time. It was observed that the mode structure was well preserved during the time of the feedback application. Several lumped parameter formulations were used to study the feedback process. The observed feedback characteristics are in good qualitative agreement with the analysis. These results provide encouragement to future efforts towards optimizing the RWM feedback methodology in parallel to what has been successfully developed for the n = 0 vertical positional control. Newly developed MHD codes have been extremely useful in guiding the experiments and in providing possible paths for the next step.

Magnetic Control of Tokamak Plasmas

Magnetic Control of Tokamak Plasmas PDF Author: Marco Ariola
Publisher: Springer
ISBN: 3319298909
Category : Technology & Engineering
Languages : en
Pages : 208

Book Description
This book is a complete treatment of work done to resolve the problems of position-, current-, and shape-control of plasma in tokamak-type (toroidal) devices being studied as a potential means of commercial energy production by nuclear fusion. Modelling and control are both detailed, allowing non-expert readers to understand the control problem. Starting from the magneto-hydro-dynamic equations, all the steps needed for the derivation of plasma state-space models are enumerated with frequent recall of the basic concepts of electromagnetics. The control problem is then described, beginning with the control of current and position—vertical and radial—control and progressing to the more challenging shape control. The solutions proposed vary from simple PIDs to more sophisticated MIMO controllers. The second edition of Magnetic Control of Tokamak Plasmas contains numerous updates and a substantial amount of completely new material covering areas such as: • modelling and control of resistive wall modes—the most important non-axisimmetric mode; • the isoflux approach for shape control; • a general approach for the control of limiter plasmas; • the use of inner vessel coils for vertical stabilization; and • significantly enhanced treatment of plasma-shape control at JET, including experimental results and introducing a method implemented for operation in the presence of current saturations. Whenever possible, coverage of the various topics is rounded out with experimental results obtained on currently existing tokamaks. The book also includes a presentation of the typical actuators and sensors used for control purposes in tokamaks. Some mathematical details are given in the appendices for the interested reader. The ideas formulated in this monograph will be of great practical help to control engineers, academic researchers and graduate students working directly with problems related to the control of nuclear fusion. They will also stimulate control researchers interested more generally in the advanced applications of the discipline. Advances in Industrial Control aims to report and encourage the transfer of technology in control engineering. The rapid development of control technology has an impact on all areas of the control discipline. The series offers an opportunity for researchers to present an extended exposition of new work in all aspects of industrial control.

Closed Loop Feedback of MHD Instabilities on DIII-D.

Closed Loop Feedback of MHD Instabilities on DIII-D. PDF Author: E. Fredrickson
Publisher:
ISBN:
Category : Magnetohydrodynamics
Languages : en
Pages : 11

Book Description


ACTIVE FEEDBACK STABILZATION OF THE RESISTIVE WALL MODE ON THE DIII-D DEVICE.

ACTIVE FEEDBACK STABILZATION OF THE RESISTIVE WALL MODE ON THE DIII-D DEVICE. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 30

Book Description
A proof of principle magnetic feedback stabilization experiment has been carried out to suppress the resistive wall mode (RWM), a branch of the ideal magnetohydrodynamic (MHD) kink mode under the influence of a stabilizing resistive wall, on the DIII-D tokamak device [Plasma Phys. and Contr. Fusion Research (International Atomic Energy Agency, Vienna, 1986), p. 159]. The RWM was successfully suppressed and the high beta duration above the no wall limit was extended to more than 50 times the resistive wall flux diffusion time. It was observed that the mode structure was well preserved during the time of the feedback application. Several lumped parameter formulations were used to study the feedback process. The observed feedback characteristics are in good qualitative agreement with the analysis. These results provide encouragement to future efforts towards optimizing the RWM feedback methodology in parallel to what has been successfully developed for the n = 0 vertical positional control. Newly developed MHD codes have been extremely useful in guiding the experiments and in providing possible paths for the next step.

Observation and Control of Resistive Wall Modes

Observation and Control of Resistive Wall Modes PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 18

Book Description
Two approaches to achieving long-time scale stabilization of the ideal kink mode with a real, finite conductivity wall are considered: plasma rotation and active feedback control, DIII-D experiments have demonstrated stabilization of the resistive wall mode (RWM) by sustaining beta greater than the no-wall limit for up to 200 ms, much longer than the wall penetration time of a few ms. These plasmas are typically terminated by an m = 3, n = 1 mode as the plasma rotation slows below a few kHz. Recent temperature profile data shows an ideal MHD mode structure, as expected for the resistive wall mode at beta above the no-wall limit. The critical rotation rate for stabilization is in qualitative agreement with recent theories for dissipative stabilization in the absence of magnetic islands. However, drag by small-amplitude RWMs or damping of stable RWMs may contribute to an observed slowing of rotation at high beta, rendering rotational stabilization more difficult. An initial open-loop active control experiment, using non-axisymmetric external coils and a new array of saddle loop detectors, has yielded encouraging results, delaying the onset of the RWM.

Study of the Resistive Wall Mode in DIII-D.

Study of the Resistive Wall Mode in DIII-D. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Book Description
Recent MHD calculations predict that, for a plasma with sufficient rotation, a resistive wall can provide stability up to the [beta]{sub N} limit predicted assuming the wall were ideal. In the region of [beta]{sub N} between the wall-at-infinity limit and the ideal-wall limit, an MHD instability branches into two modes: a plasma mode, that is nearly stationary with respect to the plasma at the resonant surface, and a resistive wall mode (RWM), that is nearly stationary with respect to the wall. Experiments conducted in the DIII-D, PBX-M and HBT-EP tokamaks have demonstrated that plasmas with a nearby conducting wall can remain stable above the beta limit predicted with wall-at-infinity, and have reported observations of instabilities with the characteristics of a resistive wall mode. In the experiments described in this paper, improved diagnostic measurements and plasma operational techniques, giving broader current density profiles and high toroidal rotation, have provided direct identification of the resistive wall mode. These experiments were designed to ease the requirements on total beta in favor of maximizing the wall stability enhancement factor, E{sub W}, increasing the duration of the wall-stabilized phase, and ensuring shot-to-shot reproducibility with the available heating power.

Proceedings of the Fourteenth Topical Meeting on the Technology of Fusion Energy, October 15-19, 2000, Park City, Utah

Proceedings of the Fourteenth Topical Meeting on the Technology of Fusion Energy, October 15-19, 2000, Park City, Utah PDF Author:
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 906

Book Description


Tokamaks

Tokamaks PDF Author: John Wesson
Publisher: Oxford University Press
ISBN: 0199592233
Category : Science
Languages : en
Pages : 828

Book Description
The tokamak is the principal tool in controlled fusion research. This book acts as an introduction to the subject and a basic reference for theory, definitions, equations, and experimental results. The fourth edition has been completely revised, describing their development of tokamaks to the point of producing significant fusion power.