TOKAMAK nuclear fusion reactors: a control perspective
The design and implementation of a control system operating within a nuclear fusion machine imply the need to deal with various issues. In particular, since in a feedback control system the presence of one or more sensors is necessary to provide the information for the derivation of the control law acting on actuators, the particular specifications emerging from the peculiar characteristics of the considered system have to be carefully evaluated. Hence, all the phases for designing a control system in a nuclear fusion plant environment should be faced.This workshop aims to present to the control scientific community, the problems related to the control of a TOKAMAK plant and the techniques developed by control and automation engineers working on them, with a particular attention to the control issues related with the next generation TOKAMAKs.
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Workshop schedule |
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| 9:00-10:00 | ITER: an introduction Dr. Anders Wallander, CODAC Section Leader of ITER An introduction on the new nuclear fusion reactor ITER which is in construction in Cadarache, France, outlining all the issues related to the control strategies which have to be implemented in the reactor. |
| 10:00-10:30 | Realtime control in next generation TOKAMAKs Dr. Filippo Sartori, Fusion for energy ITER, F4E Barcelona The issues and state of art solutions for realtime control in next generation TOKAMAKs with particular attention devoted to the ITER case will be introduced. |
| 10:30-11:00 | Remote handling in the view of ITER Dr Carlo Damiani, F4E RH project team manager, F4E Barcelona An overview on remote handling in the view of ITER and the F4E procurement strategy for remote handling. |
| 11:00-11:30 | Current, position, and shape control in tokamaks Dr Gianmaria De Tommasi, Università degli Studi di Napoli Federico II/Consorzio CREATE, Napoli, Italy This lecture first introduces a plasma linearized model, which can be efficiently used to design plasma current, shape and position control systems. Afterwards the plasma shape control and the vertical stabilization problems are presented. |
| 11:30-12:00 | Disruption prediction in tokamaks Dr Giuliana Sias, University of Cagliari, Cagliari, Italy The problems related to disruption analysis and prediction in tokamaks will be outlined. Currently adopted mapping methodologies will be outlined as regard both ASDEX and JET plants and new results on disruption prediction will be presented. |
| 12:00-12:30 | Bond Graphs for Diagnosis of hybrid systems Dr. Didier Mazon, Co-Chair EFDA Diagnostic Topical Group and EFDA Group Leader 'Feedback Control Plasma current profile determination and control, with particular attention to the JET case and with considerations towards the ITER plant. |
| 12:30-13:00 | A new discharge management system for the Frascati Tokamak Upgrade Dr. Arturo Buscarino, University of Catania, Catania, Italy The problems related to the management of input data which define each single pulse will be outlined and the already adopted strategies in the view of ITER will be described. |
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| 14:30 | Table Discussion |
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Benefits to Participants: participants will acquire a comprehensive and wide knowledge related to the design and implementation of state-of-art control strategies which will be adopted in ITER, a next generation TOKAMAK machine, which will allow to perform advanced experimental scenarios. Furthermore, participants will be informed on the building status of ITER and on the new perspectives introduced by experiments which will be performed on ITER, with particular attention to the possible insights in the view of energy production form nuclear fusion reactions. Targeted Audience: The Workshop is suitable for academicians, research scientists, both engineers and physicists, researchers in robotics and control automation, government and industry employees, and graduate students working or conducting research in control systems, electronics, sensors, nuclear physics. |
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