Abstract:An artificial neural network, combining signals from a large number of plasma diagnostics, was used to estimate the high- beta disruption boundary in the DIII-D tokamak. It is shown that inclusion of many diagnostic measurements results in a much more accurate prediction of the disruption boundary than that provided by the traditional Troyon limit. A trained neural network constitutes a non-linear, non-parametric model of the disruption boundary. Through the analysis of the input-output sensitivities, the rela… Show more
“…Methods for predicting disruption onset have been developed (e.g. [34][35][36][37]), but almost all are based on training algorithms with data. Generally, a significant quantity of disruptive data is required for such training, which is likely to be difficult in ITER, which can tolerate only a small number of major disruptions before in-vessel different control objectives may be heavily coupled.…”
Tbe tokamak concept for magnetic confinement of fusion plasmas is now quite mature scientifically. This maturity is evidenced by tbe ongoing worldwide effort to design and construct an internationally supported multi-billion dollar experimental tokamak called ITER, wbose purpose is to demonstrate the scientific and technical feasibility of fusion energy as 8 power source. To achieve its scientific objectives, tbe ITER device will need to implement solutions to several challenging control problems. Some solutions to tbese control problems are already mature, e.g. control of the plasma boundary sbape and stabilization of the vertical stability, but many otber solutions are currently in development or do not yet have viable solution approaches. In almost all cases, control solutions developed on existing tokamaks are made more challenging on ITER by safety issues arising from its nuclear mission and control actuation margins tbat are reduced due to cost considerations. However, many of these problems must ha\'e robust solutions in place before ITER comes online in approximately 2016. In this paper, we summarize a set of the most urgently needed control solutions and describe the progress made toward solving a few of these problems.
“…Methods for predicting disruption onset have been developed (e.g. [34][35][36][37]), but almost all are based on training algorithms with data. Generally, a significant quantity of disruptive data is required for such training, which is likely to be difficult in ITER, which can tolerate only a small number of major disruptions before in-vessel different control objectives may be heavily coupled.…”
Tbe tokamak concept for magnetic confinement of fusion plasmas is now quite mature scientifically. This maturity is evidenced by tbe ongoing worldwide effort to design and construct an internationally supported multi-billion dollar experimental tokamak called ITER, wbose purpose is to demonstrate the scientific and technical feasibility of fusion energy as 8 power source. To achieve its scientific objectives, tbe ITER device will need to implement solutions to several challenging control problems. Some solutions to tbese control problems are already mature, e.g. control of the plasma boundary sbape and stabilization of the vertical stability, but many otber solutions are currently in development or do not yet have viable solution approaches. In almost all cases, control solutions developed on existing tokamaks are made more challenging on ITER by safety issues arising from its nuclear mission and control actuation margins tbat are reduced due to cost considerations. However, many of these problems must ha\'e robust solutions in place before ITER comes online in approximately 2016. In this paper, we summarize a set of the most urgently needed control solutions and describe the progress made toward solving a few of these problems.
“…MLPs have been successfully used in several nuclear research applications, such as plasma control [6][7][8], plasma parameter extraction [9][10][11], Gaussian fitting [12] and online detection of disruption precursors [13,14]. The MLP architecture with BP error learning is also used in the application described in this paper.…”
Langmuir probes are used in nuclear fusion experiments to derive the electronic temperature of a high temperature ionised gas. For this purpose, the current I flowing through the probe at varying applied potentials V is measured. The shape of the resulting V-I characteristic is exponential, and depends upon the electronic temperature. Traditionally, fitting procedures are used to derive the temperature, but the amount of computation required is high as the measurement is repeated many times during the experiment. In this paper the use of neural networks to derive the electronic temperature from Langmuir probe data is investigated. Neural networks proved to be comparable with traditional methods in the accuracy of the reconstruction, though requiring less computational resources.
“…Neural networks are typically trained, in the sense that a predetermined sample of input and output data are used to determine the optimal values of the coefficients of the network. Neural networks have been used to predict various forms of disruptions on ASDEX Upgrade [84][85][86], DIII-D [87], ADITYA [88,89], TEXT [90,91], JET [85,92,93], and JT-60 [94,95].…”
Section: : Introductionmentioning
confidence: 99%
“…Typical input data to the network include a measure of the plasma β (the normalized β (β N ) [96,97] or poloidal β (β P )), edge safety factor, plasma density (or Greenwald fraction [98,99]), locked mode amplitude, input power, radiated power, shape parameters, internal inductance, confinement time, and neutron emission. Some early work also used soft X-ray emission [87][88][89]91], high(er) frequency magnetic probes [87][88][89][90], or Dα monitors [87][88][89] though these diagnostics have typically not been used in more recent studies [85,86,92,93,95].…”
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