Fusion Engineering and Design 96–97 (2015) 698–702
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Fusion Engineering and Design
jo u r n al homep age: www.elsevier.com/locate/fusengdes
Improvements in disruption prediction at ASDEX Upgrade
R. Aledda, B. Cannas, A. Fanni, A. Pau, G. Sias
∗
, the ASDEX Upgrade Team
Department of Electrical and Electronic Engineering, University of Cagliari, Italy
h i g h l i g h t s
•
A disruption prediction system for AUG, based on a logistic model, is designed.
•
The length of the disruptive phase is set for each disruption in the training set.
•
The model is tested on dataset different from that used during the training phase.
•
The generalization capability and the aging of the model have been tested.
•
The predictor performance is compared with the locked mode detector.
a r t i c l e i n f o
Article history:
Received 29 September 2014
Received in revised form 19 March 2015
Accepted 23 March 2015
Available online 16 April 2015
Keywords:
Disruption prediction
Nuclear fusion
Logistic regressor
Mahalanobis distance
a b s t r a c t
In large-scale tokamaks disruptions have the potential to create serious damage to the facility. Hence
disruptions must be avoided, but, when a disruption is unavoidable, minimizing its severity is mandatory.
A reliable detection of a disruptive event is required to trigger proper mitigation actions. To this purpose
machine learning methods have been widely studied to design disruption prediction systems at ASDEX
Upgrade. The training phase of the proposed approaches is based on the availability of disrupted and
non-disrupted discharges. In literature disruptive configurations were assumed appearing into the last
45 ms of each disruption. Even if the achieved results in terms of correct predictions were good, it has
to be highlighted that the choice of such a fixed temporal window might have limited the prediction
performance. In fact, it generates confusing information in cases of disruptions with disruptive phase
different from 45 ms.
The assessment of a specific disruptive phase for each disruptive discharge represents a relevant issue
in understanding the disruptive events. In this paper, the Mahalanobis distance is applied to define a
specific disruptive phase for each disruption, and a logistic regressor has been trained as disruption
predictor.
The results show that enhancements on the achieved performance on disruption prediction are possible
by defining a specific disruptive phase for each disruption.
© 2015 Elsevier B.V. All rights reserved.
1. Introduction
The physical phenomena leading to plasma disruptions in toka-
maks are very complex and non-linear, and the present state of
knowledge is not sufficient to explain the intrinsic structure of the
data of interest. Following a data based approach, the plasma in
a tokamak is considered as a multidimensional system which can
be described through a multidimensional set of observables, i.e.,
available diagnostic signals recorded during the experiments.
∗
Corresponding author. Tel.: +39 0706755878; fax: +39 0706755900.
E-mail addresses: raffaele.aledda@diee.unica.it (R. Aledda), cannas@diee.unica.it
(B. Cannas), fanni@diee.unica.it (A. Fanni), alessandro.pau@diee.unica.it (A. Pau),
giuliana.sias@diee.unica.it (G. Sias).
To this purpose data-based methods have been widely studied
to design disruption prediction systems on several experimental
devices. In particular, for ASDEX Upgrade (AUG), literature pro-
posed predictive systems applying data-based techniques, such as
Multi-layer Perceptron neural networks [1,2], Discriminant Analy-
sis [3], and Self-Organizing Maps [4]. Moreover, for JET the neural
network approaches have been widely applied for disruption pre-
diction both for carbon wall [5–7] and full metal ITER-like wall
[8]. For the spherical torus NSTX a disruption predictor based on
a multivariate statistical analysis of diagnostic data is proposed [9].
The training phase of the proposed approaches is based on the
availability of disrupted and non-disrupted discharges. To accom-
plish an exhaustive model, every disruptive and safe configuration
included in the machine operational space should be represented
in the training set. Safe configurations were selected from safe
http://dx.doi.org/10.1016/j.fusengdes.2015.03.045
0920-3796/© 2015 Elsevier B.V. All rights reserved.