Papers by filippo sartori
Fusion Engineering and Design
Several design variants of chopper-based digital signal integrators have been tested to evaluate ... more Several design variants of chopper-based digital signal integrators have been tested to evaluate the optimal solution to achieve the ITER magnetics diagnostic requirements. A maximum flux-equivalent drift of 500 μ V.s/ hour is one of the key ITER magnetics diagnostic constraints for the integrators. The flux drift must be below the specified limit whilst the device satisfies other stringent specifications such as, 500 V galvanic isolation, 14-bit ENOB and environment magnetic field tolerance up to 10 mT. This paper presents the results of some of the tests performed on the integrator prototypes developed. These include tests to verify the integrator drift during long experiments when subjected to different conditions, e.g., imposition of a common mode voltage and input signals with a frequency spectrum that challenges the design limits.
IAEA Fusion Energy Conference (FEC), Kyoto, J, October 17-22, 2016, 2016
The JT-60SA tokamak, being built under the Broader Approach agreement jointly by Europe and Japan... more The JT-60SA tokamak, being built under the Broader Approach agreement jointly by Europe and Japan, is due to start operation in 2020 and is expected to give substantial contributions to both ITER and DEMO scenario optimisation. A broad set of preparation activities for an efficient start of the experiments on JT-60SA is being carried out, involving elaboration of the Research Plan, advanced modelling in various domains, feasibility and conception studies of diagnostics and other subsystems in connection with the priorities of the scientific programme, development and validation of operation tools. The logic and coherence of this approach, as well as the most significant results of the main activities undertaken are presented and summarised.
Fusion Engineering and Design, 2018
Nuclear Fusion, 2017
Experiments have been carried out on the MAST and JET tokamaks intended to compare the electrical... more Experiments have been carried out on the MAST and JET tokamaks intended to compare the electrical resistivity of the plasma with theoretical formulations. The tests consist of obtaining motional stark effect (MSE) measurements in MHD-free plasmas during plasma current ramp-up (JET and MAST), ramp-down (MAST) and in stationary state (JET and MAST). Simulations of these plasmas are then performed in which the current profile evolution is calculated according to the poloidal field diffusion equation (PFDE) with classical or neoclassical resistivity. Synthetic MSE data are produced in the simulations for direct comparison with the experimental data. It is found that the toroidal current profile evolution modelled using neoclassical resistivity did not match the experimental observations on either device during current ramp-up or ramp-down as concluded from comparison of experimental and synthetic MSE profiles. In these phases, use of neoclassical resistivity in the modelling systematically overestimates the rate of current profile evolution. During the stationary state however, the modelled toroidal current profile matched experimental observations to a high degree of accuracy on both devices using neoclassical resistivity. Whilst no solution to the mismatch in the dynamic phases of the plasma is proposed, it is suggested that some physical process other than MHD which is not captured by the simple diffusive model of current profile evolution is responsible.
Fusion Engineering and Design, 2019
A Test Facility (TF) has been designed and installed at SPC to allow for the commissioning of the... more A Test Facility (TF) has been designed and installed at SPC to allow for the commissioning of the EU gyrotrons developed in view of their integration to the ITER EC system. The first phase of operation of this TF was dedicated to the development of the EU 2 MW coaxial cavity gyrotron [1,2]. The EU gyrotron development for ITER has been reoriented since then and is presently advancing a 170 GHz/ 1MW/CW gyrotron developed within the EGYC consortium and manufactured by THALES. At the same time, the TF has been enhanced to host the FALCON project [3], consisting in the integration of a second 170 GHz/1MW/ CW gyrotron delivered by GYCOM. This new experiment is aiming to test the main RF components of the EC Transmission Line (TL) and of the Upper Launcher system to be installed on ITER. This paper describes the technical modifications brought to the existing TF to comply with the requirements of both 1 MW gyrotrons operation. Effort has been put in switching of the auxiliaries from one tower to the other within a short time (< 1 week) while maintaining operator safety and equipment protection. A detailed description of the additional implementation and of the strategy followed to share the main auxiliaries (like the HVPS, the cooling system, the control system, etc.) will be presented. Moreover, most of the new equipment, such as the control hardware, have been designed to fulfil ITER site standards. Finally, the preliminary operation results with this reconfigured TF will be presented. 150 mA) supplying the body, will be connected either to the EU 1MW
AIP Conference Proceedings, 2001
In the initial phase of ITER operation, 4 He plasmas could be used in order to avoid activating t... more In the initial phase of ITER operation, 4 He plasmas could be used in order to avoid activating the machine. The main ICRH scenarios foreseen for ITER 4 He plasmas are (3 He) 4 He and (H) 4 He. ICRH experiments have been carried out on JET using 4 He plasmas to validate these scenarios. At the same time, conditions for access to H-mode in plasmas of various isotope compositions from dominantly 4 He to dominantly D have been studied. Experiments have also been carried out for the first time in 4 He plasmas with the ICRF power added to 4 He neutral beam injection at the third harmonic of 4 He in order to produce a 4 He tail for alpha particle studies.
IFAC Proceedings Volumes, 2005
Fusion Science and Technology, 2008
Advance tokamak (AT) scenarios are gaining more and more importance in operating tokamaks. These ... more Advance tokamak (AT) scenarios are gaining more and more importance in operating tokamaks. These scenarios pose challenging control problems, since they require the simultaneous achievement of ambitious plasma parameters. The inherent coupling among the various variables calls for an integrated approach for the design of the controllers. This paper describes an example of integrated design recently implemented at JET: the control of plasma shape and boundary flux. After a brief description of the control problem, the paper focuses on the solution that has been adopted, presenting the technical details of the control scheme. The experimental results included in the paper are in agreement with the expected simulation results, and demonstrate the effectiveness of the proposed solution.
Fusion Engineering and Design, 2017
h i g h l i g h t s • The implementation of the Central Interlock System of the ITER full-size io... more h i g h l i g h t s • The implementation of the Central Interlock System of the ITER full-size ion source in the Neutral Beam Test Facility is reported. • Fast and slow interlock functions need reaction times faster than 10 s and 100 ms, respectively. • Slow interlock is implemented by Siemens PLCs and WinCC OA SCADA. • Fast interlock is implemented by National Instruments CompactRIO.
IFAC Proceedings Volumes, 2006
how an automation project should be structured the programming languages that can be used by the ... more how an automation project should be structured the programming languages that can be used by the developers De Tommasi-Di Sanzo-Pironti Advances in Control Education 2006-ACE'06 Outline Introduction UniSim Exmaple Conclusions UniSim UniSim is an educational tool developed at University of Naples UniSim can be used to design automation software which complies with IEC 61131-3 UniSim allows to avoid the choice of a specific commercial platform when teaching PLCs programming. Thanks to its simulation engine, UniSim allows to validate off − line the developed software UniSim can be used to fast prototype the automation systems using a desktop equipped with low-cost I/O boards De Tommasi-Di Sanzo-Pironti Advances in Control Education 2006-ACE'06 Outline Introduction UniSim Exmaple Conclusions UniSim UniSim is an educational tool developed at University of Naples UniSim can be used to design automation software which complies with IEC 61131-3 UniSim allows to avoid the choice of a specific commercial platform when teaching PLCs programming. Thanks to its simulation engine, UniSim allows to validate off − line the developed software UniSim can be used to fast prototype the automation systems using a desktop equipped with low-cost I/O boards De Tommasi-Di Sanzo-Pironti Advances in Control Education 2006-ACE'06 Outline Introduction UniSim Exmaple Conclusions UniSim UniSim is an educational tool developed at University of Naples UniSim can be used to design automation software which complies with IEC 61131-3 UniSim allows to avoid the choice of a specific commercial platform when teaching PLCs programming. Thanks to its simulation engine, UniSim allows to validate off − line the developed software UniSim can be used to fast prototype the automation systems using a desktop equipped with low-cost I/O boards De Tommasi-Di Sanzo-Pironti Advances in Control Education 2006-ACE'06 Outline Introduction UniSim Exmaple Conclusions UniSim UniSim is an educational tool developed at University of Naples UniSim can be used to design automation software which complies with IEC 61131-3 UniSim allows to avoid the choice of a specific commercial platform when teaching PLCs programming. Thanks to its simulation engine, UniSim allows to validate off − line the developed software UniSim can be used to fast prototype the automation systems using a desktop equipped with low-cost I/O boards De Tommasi-Di Sanzo-Pironti Advances in Control Education 2006-ACE'06 UniSim interfaces with off-the-shelf I/O boards, thus it can be used during lab activities Labs do not need to be equipped with a large number of expensive commercial PLC platforms UniSim makes use of the XML Formats for IEC 61131-3 to import/export the projects. This feature give the possibility to reuse the developed software on a commercial platform → portability De Tommasi-Di Sanzo-Pironti Advances in Control Education 2006-ACE'06 Outline Introduction UniSim Exmaple Conclusions. . .moreover.. . UniSim can be used by the teacher-in the classroom to work out examples by students-when solving their homework UniSim interfaces with off-the-shelf I/O boards, thus it can be used during lab activities Labs do not need to be equipped with a large number of expensive commercial PLC platforms UniSim makes use of the XML Formats for IEC 61131-3 to import/export the projects. This feature give the possibility to reuse the developed software on a commercial platform → portability De Tommasi-Di Sanzo-Pironti Advances in Control Education 2006-ACE'06 Outline Introduction UniSim Exmaple Conclusions. . .moreover.. . UniSim can be used by the teacher-in the classroom to work out examples by students-when solving their homework UniSim interfaces with off-the-shelf I/O boards, thus it can be used during lab activities Labs do not need to be equipped with a large number of expensive commercial PLC platforms UniSim makes use of the XML Formats for IEC 61131-3 to import/export the projects. This feature give the possibility to reuse the developed software on a commercial platform → portability
Fusion Engineering and Design, 2017
The main goal of this work is to demonstrate that a digital integrator based on the signal choppi... more The main goal of this work is to demonstrate that a digital integrator based on the signal chopping concept is capable of attaining the ITER requirements. In particular, the ITER magnetics diagnostic requires a maximum flux drift of 500 V s/hour, among other specifications, for the signal integrators. As of today, known commercial integration modules do not fully comply simultaneously with all ITER magnetics requirements. A first phase of prototyping, presented in this work, comprises the development and testing of four design variants. Combinations of a SAR ADC (AD7960) and a Delta-Sigma ADC (ADS1675) with different analog front ends were used for the corresponding integrator prototypes. The designs have a common interface to an FPGA based system that receives the data acquired during the tests and streams it through a GbE link to a PC, where real-time digital integration of the signals is performed using the MARTe control framework. The GbE network also acts as the interfacing medium for the data archiving, through the connection of the integrator prototypes under test to an MDSplus based environment. This paper presents the integrator prototype designs developed and tests done so far.
AIP Conference Proceedings, 2008
The achievement of long duration, alternating current discharges on the tokamak IST-TOK requires ... more The achievement of long duration, alternating current discharges on the tokamak IST-TOK requires a real-time plasma position control system. The plasma position determination based on magnetic probes system has been found to be inadequate during the current inversion due to the reduced plasma current. A tomography diagnostic has been therefore installed to supply the required feedback to the control system. Several tomographic methods are available for soft X-ray or bolometric tomography, among which the Cormack and Neural networks methods stand out due to their inherent speed of up to 1000 reconstructions per second, with currently available technology. This paper discusses the application of these algorithms on fusion devices while comparing performance and reliability of the results. It has been found that although the Cormack based inversion proved to be faster, the neural networks reconstruction has fewer artifacts and is more accurate.
AIP Conference Proceedings, 2008
Fusion Engineering and Design, 2015
ABSTRACT The Plasma Control System Simulation Platform (PCSSP) is a highly flexible, modular, tim... more ABSTRACT The Plasma Control System Simulation Platform (PCSSP) is a highly flexible, modular, time-dependent simulation environment developed primarily to support development of the ITER Plasma Control System (PCS). It has been under development since 2011 and is scheduled for first release to users in the ITER Organization (IO) and at selected additional sites in 2015. Modules presently implemented in PCSSP enable exploration of axisymmetric evolution and control, basic kinetic control, and tearing mode suppression. A basic capability for generation of control-relevant events is included, enabling study of exception handling in the PCS, continuous controllers, and PCS architecture. While the control design focus of PCSSP applications tends to require only a moderate level of accuracy and complexity in modules, more complex codes can be embedded or connected to access higher accuracy if needed. This paper describes the background and motivation for PCSSP, provides an overview of the capabilities, architecture, and features of PCSSP, and discusses details of the PCSSP vision and its intended goals and application. Completed work, including architectural design, prototype implementation, reference documents, and IO demonstration of PCSSP, is summarized and example use of PCSSP is illustrated. Near-term high-level objectives are summarized and include preparation for release of an “alpha” version of PCSSP and preparation for the next development phase. High-level objectives for future work are also discussed.
Fusion Engineering and Design, 2014
Fusion Engineering and Design, 2014
IFAC Proceedings Volumes, 2005
Journal of Infrared, Millimeter, and Terahertz Waves, 2015
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Papers by filippo sartori