SAMI (Synthetic Aperture Microwave Imaging): Measuring tokamak plasma current using electron Bernstein wave emission

Lead Research Organisation: University of York
Department Name: Physics

Abstract

This research project will apply aperture synthesis, a diagnostic technique used routinely in radio astronomy, to make the first time-resolved measurements of the current density in the tokamak plasma edge. This measurement is crucial for understanding violent eruptions known as ELMs which could be extremely damaging for ITER, the next generation fusion device. At EUR10Bn, ITER is one of the largest international science projects on Earth.Fusion involves making two positively-charged nuclei collide to produce a heavier nucleus, releasing energy in the process. This can only occur at temperatures of about 100 million degrees. The fundamental challenge to performing fusion is to confine the hot ionised gas (plasma) sufficiently well. The principle behind the leading candidate design for a fusion power plant (called a tokamak) is to use the fact that the charged particles of the plasma state respond to electromagnetic fields, which can be used to confine them away from the material walls of the device. If sufficient heating power is injected into a tokamak plasma, then it enters a high-confinement mode. In this mode, the thermal energy of the plasma increases by about a factor of two due to the creation of a highly insulating layer near the plasma edge, which is typically only a few centimetres thick, compared to the body of the plasma which can be a metre or so across. The pressure gradient in this edge layer is extremely high, so there is a vulnerability to instabilities. The plasma experiences a repetitive series of violent plasma eruptions called Edge Localised Modes, or ELMs, which expel large amounts of energy typically within about a hundred millionths of a second. These are an interesting scientific phenomenon on today's tokamaks but on ITER, where the ejected power in an ELM is expected to be an order of magnitude larger, they could cause serious damage if not controlled. There are ideas for how to control ELMs that work on existing tokamaks, but to extrapolate them reliably to ITER requires a more detailed understanding of the physics. In order to test and constrain theoretical models for ELMs, we need to be able to measure the current density and pressure gradient in the thin edge layer. While a number of tokamaks have a good measurement of the pressure gradient, the current density is much more challenging, and the role of the current density in ELMs remains unconfirmed experimentally.This project will develop a novel diagnostic technique to measure the edge current density on the MAST tokamak routinely (in the sense that in principle the process could be automated). Our diagnostic technique will also have good time resolution, being able to make several measurements of the edge current density through an ELM and address the intriguing question of how (or whether) the current density is flushed out of the plasma edge region within the ELM time-scale (ie about 100 microseconds).The physical basis for this diagnostic technique is the directional emission of electron Bernstein wave (EBW) radiation, which is an example of electron cyclotron emission (ECE). Bernstein waves are electrostatic plasma waves generated in the plasma core at frequencies typically around tens of gigahertz. Most of these outgoing waves are reflected back into the core from a cut-off layer, but waves travelling at a particular angle with respect to the equilibrium magnetic field undergo a mode conversion to an electromagnetic wave that enables them to travel to the plasma edge and to be observed. The EBW emission profile allows us to measure both the direction of the magnetic field, and the rate at which it is changing. Since we know the absolute value of the toroidal magnetic field (it varies inversely proportionally with the distance from the centre of the device), we can use the rate of change of direction of the field to calculate the current density.

Publications

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Brunner KJ (2016) Modifications to the synthetic aperture microwave imaging diagnostic. in The Review of scientific instruments

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Chapman I (2015) Overview of MAST results in Nuclear Fusion

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Chorley J (2017) GPU-Based Data Processing for 2-D Microwave Imaging on MAST in Fusion Science and Technology

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Freethy S (2013) Lensless passive and active microwave imaging on MAST in Plasma Physics and Controlled Fusion

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Freethy S (2015) Localised Microwave Bursts During ELMs on MAST in EPJ Web of Conferences

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Lloyd B (2011) Overview of physics results from MAST in Nuclear Fusion

 
Description We developed a novel 2-D microwave imaging system for tokamak plasmas and successfully deployed it on the MAST experiment at the UK's Culham Centre for Fusion Energy. We obtained the first ever "camera images" of spontaneous mode-converted microwave emission from a spherical tokamak. We also actively probed the plasma with injected microwaves and measured both the intensity and Doppler shift of the back-scattered radiation. This has enabled the first-ever measurements of tokamak plasma edge magnetic pitch angle using microwave techniques: as part of future work we anticipate that this technique will form the basis of the routine measurements of the edge current density, which are crucial for the development and constraint of models of tokamak stability.
Exploitation Route The prototype imaging system we developed in this grant is being upgraded and enhanced to make production-quality measurements on tokamaks in the UK and overseas.
The lensless imaging methodology that we developed in this project is being taken forward to develop a microwave imaging system for medical applications.
Sectors Electronics,Energy,Healthcare

 
Description The imaging and data acquisition methodologies that have been developed through this grant is being exploited via a recently-awarded Knowledge Transfer Partnership with an industrial collaborator to develop a novel medical microwave imaging system.
First Year Of Impact 2014
Sector Energy,Healthcare
 
Description EuroFusion Enabling Research
Amount £81,722 (GBP)
Funding ID ER-WP15_CCFE-03 
Organisation EUROfusion 
Sector Public
Country European Union (EU)
Start 01/2015 
End 12/2016
 
Description Knowledge Transfer Partnership
Amount £156,468 (GBP)
Funding ID 509387 
Organisation Innovate UK 
Sector Public
Country United Kingdom
Start 05/2015 
End 04/2018