Chinese Fusion Experimental Tokamak Reactor (CFETR) started its engineering design since early 2018. A set of R&D aiming at establishing the technical basis for CFETR has also started recently. To meet CFETR design requirements, the domestic specific CFETR network and the design database has been established to facilitate the team data and design sharing and consistency. The document...
SST-1 timing system is a real time event based trigger generation and distribution system used for the synchronized operation of its various heterogeneous and distributed sub-systems during the plasma discharges. The VME based platform dependent old timing system is exhausted with spares inventory during long period of its existence and also had interface issues with the hardware advancement...
The JET control and data acquisition system (CODAS) is an integrated system that provides all the pulse based and continuous data acquisition, real time and slow control and control room interfaces for JET. It has a long history, dating back to the beginning of JET in 1980. It utilises both commercially available hardware along with many in-house modules. The software has grown up and evolved...
An overview of advances and progress on the KSTAR plasma control improvement is given. The enhancement of the plasma control system continues in order to enable implementations of more sophisticated control algorithms and capabilities of integrated controls on magnets, gas, heating and off-normal event handling. Features and functionalities are constantly added for integration of various...
The DIII-D Plasma Control System (PCS) is a comprehensive software and hardware system used in real-time data acquisition and feedback control of numerous actuators on the DIII-D tokamak. It regulates hundreds of plasma characteristics including shape, position, divertor function, and core performance. The custom software developed at DIII-D provides an expandable platform from which new...
The divertor heat flux is one of the major concerns for high performance and long pulse plasma operation, since it may lead to unacceptable heat load and thus damage the divertor target material. EAST has achieved a total power injection up to 0.3 GJ with ITER-like water-cooled tungsten (W) mono-block divertor. The active divertor heat flux feedback control is urgently needed in EAST.
EAST...
MARTe is a framework for real-time control that has been used in several fusion experiments. Recently, a new version named MARTe2 has been developed adhering to software quality standards. The framework supervises data movement and component interaction in real-time and is based on configuration information specifying the involved threads, the computation and the data management components....
In order to increase the safety, it is more important than ever to generate a signal to turn off the device even when the abnormal situation occurs during the plasma discharge. KSTAR has built the Fast Interlock System (FIS) since achieving first plasma in 2008, and built and operated the 4th version of FIS which using NI c-RIO technology in 2018 [1].
We moved the safety related...
Control, Data Acquisition and Communication (CODAC) real-time software codes are key elements for the operation of a fusion device as they can play a key role both for the machine protection and for the optimization of the experiments. In 2013, following the WEST project (W -for tungsten- Environment Steady-state Tokamak) upgrade, the whole legacy acquisition system has been refactored.
The...
During the early campaigns of the KSTAR projgect, feedback control of plasma density has been successfully commissioned at the very first attempt by using a transfer function analysis. A stable and robust discharge was chosen as a test-bed i.e. a 300 kA ($I_p$) 2.0 T ($B_t$) ohmic circular limited plasma. Before direct feedback control, pre-programmed fueling modulation was carried out by...
It has been widely accepted that a high confinement mode(H-mode) operation is necessary for advanced tokamaks or ITER. However, when plasma is in H-mode, the edge localized mode (ELM) occurs at the plasma edge, which release particles and energy [1]. In case of ITER, a full tungsten divertor cannot tolerate the heat load from the type-I ELM [2]. Besides, in terms of plasma density feedback...
MAST has undergone a substantial upgrade [1], featuring among other things several new poloidal field coils mostly distributed around the new closed-throat divertor structure and an enlarged centre column. The considerable changes have required the plasma control software to be substantially re-written.
The MAST digital plasma control system [2] was based on an architecture developed by...
Control and data acquisition systems of Thailand Tokamak 1 (TT1) are designed and developed as tools for researchers and students in Asian country. The control and data acquisition systems is designed base on the PXI platforms and synchronized with a precision time protocol (PTP), defined in the IEEE 1588 standard. The PXI6683 cards are used as a timing module in PXI cases, time resolution up...
An upgrade is being conducted on the TCABR tokamak, which is a small-size tokamak (R0 = 0.62 m and a = 0.2 m) operated at the University of São Paulo, Brazil. An important part of this upgrade is the installation of additional poloidal field coils to allow for the generation of various divertor configurations such as single-null, double-null, snowflake and x-point target divertors. The control...
An upgrade is being conducted on the TCABR tokamak, which is a small-size tokamak (R0 = 0.62 m and a = 0.2 m) operated at the University of São Paulo, Brazil. This upgrade consists mainly in the installation of (i) graphite tiles to cover entirely the inner surface of the vacuum vessel wall, (ii) new poloidal field (PF) coils to allow for the generation of various divertor configurations such...
This work mainly describes the progress and preparations for first plasma control in HL-2M, a medium-size copper tokamak currently under construction in China, with 16 poloidal field coils and one central solenoid (CS) coil (or Ohmic coil). Significant progress has been made in plasma control system (PCS), first plasma scenario. The proposed framework of PCS is consisted of plasma discharge...
This work provides a general overview of an upgrade that is being conducted on the TCABR tokamak, which is a small-size tokamak (R0 = 0.62 m and a = 0.2 m) operated at the University of São Paulo, Brazil. This upgrade consists mainly in the installation of (i) graphite tiles to cover entirely the inner surface of the vacuum vessel wall, (ii) new poloidal field (PF) coils to allow for the...
The experimental data obtained from the campaign dedicated to Baseline scenario for DT (deuterium-tritium) at Joint European Torus (JET) is being investigated in the frame of EUROfusion’s programme. The development of reliable ~4.0 MA scenario at q95 ~ 2.7‐3 compatible with DT operation and pulse length of 5s together with the optimization of the scenario for high performance at 4.0 MA to...
An overview of advances and progress on the KSTAR plasma control improvement is given. The enhancement of the plasma control system continues in order to enable implementations of more sophisticated control algorithms and capabilities of integrated controls on magnets, gas, heating and off-normal event handling. Features and functionalities are constantly added for integration of various...
This work provides a general overview of an upgrade that is being conducted on the TCABR tokamak, which is a small-size tokamak (R0 = 0.62 m and a = 0.2 m) operated at the University of São Paulo, Brazil. This upgrade consists mainly in the installation of (i) graphite tiles to cover entirely the inner surface of the vacuum vessel wall, (ii) new poloidal field (PF) coils to allow for the...
The DIII-D Plasma Control System (PCS) is a comprehensive software and hardware system used in real-time data acquisition and feedback control of numerous actuators on the DIII-D tokamak. It regulates hundreds of plasma characteristics including shape, position, divertor function, and core performance. The custom software developed at DIII-D provides an expandable platform from which new...
SST-1 timing system is a real time event based trigger generation and distribution system used for the synchronized operation of its various heterogeneous and distributed sub-systems during the plasma discharges. The VME based platform dependent old timing system is exhausted with spares inventory during long period of its existence and also had interface issues with the hardware advancement...
Control and data acquisition systems of Thailand Tokamak 1 (TT1) are designed and developed as tools for researchers and students in Asian country. The control and data acquisition systems is designed base on the PXI platforms and synchronized with a precision time protocol (PTP), defined in the IEEE 1588 standard. The PXI6683 cards are used as a timing module in PXI cases, time resolution up...
The experimental data obtained from the campaign dedicated to Baseline scenario for DT (deuterium-tritium) at Joint European Torus (JET) is being investigated in the frame of EUROfusion’s programme. The development of reliable ~4.0 MA scenario at q95 ~ 2.7‐3 compatible with DT operation and pulse length of 5s together with the optimization of the scenario for high performance at 4.0 MA to...
An upgrade is being conducted on the TCABR tokamak, which is a small-size tokamak (R0 = 0.62 m and a = 0.2 m) operated at the University of São Paulo, Brazil. This upgrade consists mainly in the installation of (i) graphite tiles to cover entirely the inner surface of the vacuum vessel wall, (ii) new poloidal field (PF) coils to allow for the generation of various divertor configurations such...
An upgrade is being conducted on the TCABR tokamak, which is a small-size tokamak (R0 = 0.62 m and a = 0.2 m) operated at the University of São Paulo, Brazil. An important part of this upgrade is the installation of additional poloidal field coils to allow for the generation of various divertor configurations such as single-null, double-null, snowflake and x-point target divertors. The control...
Chinese Fusion Experimental Tokamak Reactor (CFETR) started its engineering design since early 2018. A set of R&D aiming at establishing the technical basis for CFETR has also started recently. To meet CFETR design requirements, the domestic specific CFETR network and the design database has been established to facilitate the team data and design sharing and consistency. The document...
The JET control and data acquisition system (CODAS) is an integrated system that provides
all the pulse based and continuous data acquisition, real time and slow control and control
room interfaces for JET. It has a long history, dating back to the beginning of JET in 1980. It
utilises both commercially available hardware along with many in-house modules. The
software has grown up and evolved...
During the early campaigns of the KSTAR projgect, feedback control of plasma density has been successfully commissioned at the very first attempt by using a transfer function analysis. A stable and robust discharge was chosen as a test-bed i.e. a 300 kA ($I_p$) 2.0 T ($B_t$) ohmic circular limited plasma. Before direct feedback control, pre-programmed fueling modulation was carried out by...
MARTe is a framework for real-time control that has been used in several fusion experiments. Recently, a new version named MARTe2 has been developed adhering to software quality standards. The framework supervises data movement and component interaction in real-time and is based on configuration information specifying the involved threads, the computation and the data management components....
This work mainly describes the progress and preparations for first plasma control in HL-2M, a medium-size copper tokamak currently under construction in China, with 16 poloidal field coils and one central solenoid (CS) coil (or Ohmic coil). Significant progress has been made in plasma control system (PCS), first plasma scenario. The proposed framework of PCS is consisted of plasma discharge...
It has been widely accepted that a high confinement mode(H-mode) operation is necessary for advanced tokamaks or ITER. However, when plasma is in H-mode, the edge localized mode (ELM) occurs at the plasma edge, which release particles and energy [1]. In case of ITER, a full tungsten divertor cannot tolerate the heat load from the type-I ELM [2]. Besides, in terms of plasma density feedback...
Q.P. Yuan1, K. Wu1,2, L. Wang1, J.C. Xu1, K.D. Li1, R.R. Zhang1, Z.P. Luo1, J.B. Liu1, B.J. X1,2, D. Eldon3, A. Hyatt3
1Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, China
2School of Nuclear Science & Technology, University of Science & Technology of China
3 General Atomics, San Diego, CA, USA
The divertor heat flux is one of the major concerns for high performance and...
MAST has undergone a substantial upgrade [1], featuring among other things several new poloidal field coils mostly distributed around the new closed-throat divertor structure and an enlarged centre column. The considerable changes have required the plasma control software to be substantially re-written.
The MAST digital plasma control system [2] was based on an architecture developed by...
G. Caulier (a), J. Colnel (a), B. Santraine (a), N. Ravenel (a), and the WEST Team
(a) CEA-IRFM, F-13108 Saint-Paul-Lez-Durance, France
Abstract
COntrol, Data Acquisition and Communication (CODAC) real-time software codes are key elements for the operation of a fusion device as they can play a key role both for the machine protection and for the optimization of the experiments. In...
Anomaly detection refers to the problem of finding patterns in data that do not conform to expected behavior. These off-normal patterns are often referred to as anomalies, outliers, discordant observations, or exceptions in different application domains. The importance of anomaly detection is due to the fact that anomalies in data frequently involves significant and critical information in...
Big data analytics deals with heterogeneous, complex and massive datasets to identify patterns that are hidden inside enormous volumes of data. ITER is expected to acquire more than 1 Tbyte of data per discharge. This amount of data comes from hundreds of thousands of signals acquired in each discharge. Signals can be time/amplitude series, temporal evolution of profiles and video-movies...
Existing disruption predictor based on machine learning techniques, have good prediction performance but all these methods need large training datasets with many disruptions to develop successful predictors. Future machines are unlikely to provide enough disruption samples since they cause excessive machine damage and these models cannot extrapolate to machines other than it was trained on. In...
Based on the deep learning method, this paper introduced a set of ELM real-time recognition system on HL-2A. The system uses 5200 shots data (about 241,900 data slices) for learning. After more than 70 adjustments, a 22-layer convolutional neural network is obtained. The network can recognize whether a 30ms data slice contains the ELM signal, After smoothing, the system can recognize the ELMy...
New fusion research experiments will generate massive experimental data. For example, ITER will have above one million of variables from control signals and diagnostic systems. Some of these variables will produce data during long pulse (about 30 minutes) experiments and other will generate data continuously. Just to have a clearer idea of the problem, ITER estimates more than 10 GBytes/second...
Machine learning based disruption prediction method have exhibited good prediction performance with higher success rate, low false alarm rate and earlier warning time than physics based methods. One important thing pushed recent advances in machine learning field is high-quality training data. So a database with rich set of accurate disruption related labels is crucial to the development of a...
Thanks to their flexibility, FPGA-based Data Acquisition (DAQ) and processing systems are well suited to develop applications that are standard, modular, maintainable and scalable. There is currently a variety of FPGA-based solutions implementing DAQ systems and there are different approaches to design the hardware inside the FPGA. Each approach has its advantages and drawbacks, in terms of...
The KSTAR has MSE (Motional Stark Effect) diagnostics devices for measurement of plasma current density distribution. Real-time MSE is an essential diagnostic for advanced control over the q-profile in tokamaks [1]. The KSTAR MSE diagnostic data measurement system measures and stores a total of 25 signals and 2 reference signals at a rate of 2MHz sample per second. The KSTAR has developed the...
MDSplus is a software tool dedicated to data acquisition, storage and analysis used for complex scientific experiments. MDSplus has been used for data managment for fusion experiments for years, and this paper will demonstrate it can be used for a wide variety of systems as well. We will show how to set up a very simple experiment, manage data retrival, storage and consumtion using MDSplus and...
Like any advanced tokamak devices, high heat flux to the divertor target is always a crucial issue for EAST to operate in high performance and steady sate [1]. Advanced magnetic diverted configuration, like snowflake (SF) and X-divertor, is one of the attractive methods to spread the heat fluxes over divertor targets in tokamak because of enhanced scrape-off layer transport and an increased...
The integration of advanced control schemes is becoming more important as the development of fusion experiments progresses.
The ASDEX Upgrade discharge control system (DCS) is designed to be adaptable via configuration, no recompilation is necessary to change the behaviour of the control system.
In order to enable advanced control schemes the required information has to be available during the...
PPPL and Columbia University are together building a solution for analyzing rotating magnetohydrodynamic (MHD) mode measurements in real-time on KSTAR for use in new KSTAR Plasma Control System (PCS) algorithms supporting disruption prediction and avoidance research on KSTAR. The KSTAR PCS is based on the General Atomics (GA) PCS and uses the same software infrastructure with a Reflective...
GLAST is a series of small spherical tokamaks with an insulating vacuum vessel of major and minor radius of 20 and 10 cm respectively (for GLAST III). It is installed in NTFP, Islamabad, Pakistan. The purpose of these experiments is to understand different aspects of tokamak operation such as startup phase and then sustaining tokamak plasma for a sufficiently long time. In case of a...
Since 1988, the Tore Supra limiter tokamak at CEA Cadarache has been in operation, and obtained the record of the longest plasma duration of 6 minutes 30 seconds and over 1000 MJ of energy injected and extracted. In 2013 Tore Supra went through major changes to become the WEST tokamak (Tungsten Environment in Steady state Tokamak). The tokamak was upgraded into an X point divertor device....
The co-ordination of many processes/threads across many machines is a task intrinsic to plant, acquisition and machine control for all sufficiently complicated experimental devices. Although Inter-Process-Communication protocols have been developed for many applications, following decades of Tokamak operations at the Swiss Plasma Center, we decided to ask what specific messages, specifically...
The authors have been porting post data analysis systems used for the LHD project to the KSTAR project. The first one is AutoAna, or Automatic Analysis System. It is a system to manage programs to produce physical data for the LHD experiment. All the physical data for the LHD experiment is stored in the Kaiseki Server, or Analysis Server. Until the end of the fiscal year 2018, the Kaiseki...
In modern fusion experiments, the remote data access has already come into wide use in both domestic and international research collaborations. SNET mutual data exchanging platform in Japan interconnects four fusion experimental sites, LHD, QUEST, GAMMA10, and TST-2, over 1 000 km distance and enables the remote collaborators access each site’s data seamlessly as if they were in local site....
The energy-sweeping mode was recently used for measurement of the charge exchange flux energy distribution every 3-5ms via single-channel electrostatic neutral particle analyzer (NPA) in stellarator U-3M [1].The magnetic mass-separation (MS) part of NPA was omitted during these energy-sweeping measurements.The MS part is required for some experimental conditions in a case of presents of...
MITICA is the prototype of the ITER full-size Heating Neutral Beam injector (HNB). It is being installed in the Neutral Beam Test Facility established at Consorzio RFX in Padova, Italy. The operation of MITICA requires the integrated collaboration of a large set of plant systems, including high-voltage power supply (-1MV / 60 A), radio frequency power supply (4 generators, 0.9 – 1. 1 MHz / 200...
Successful reproduction of advanced tokamak scenarios in burning plasmas like ITER will strongly rely on sophisticated plasma control systems. Among the novel control physics challenges required to accomplish the control needed for scenario execution, the internal profile regulation plays a fundamental role [1]. The non-linear dynamics involved in current profile control are described by the...
Fenix [1] is the ASDEX Upgrade (AUG) flight simulator based on the 1-D ASTRA transport code coupled with the 2-D SPIDER equilibrium solver [2] and Simulink (simulation platform from MATLAB). Fenix is designed to simulate, prior every discharge, the entire discharge starting from ramping the Toroidal Field coils (TF), plasma start-up, flat-top and ramp down and finishing with ramping down the...
Across research disciplines, the size, complexity, and heterogeneity of data sets is growing rapidly. Large projects are often long-running collaborations between evolving groups of researchers. Integrating and documenting these large heterogeneous data collections is a requirement for these data to be exploited, and for them to retain their value and meaning over time. The traditional...
Advancements in data collection techniques call for the use of MDSplus not just as a centralized server, but running close to the data collection devices as well. To facilitate this, a set of Docker images are being developed to deploy miniature, self-contained installations of MDSplus. The goal being that every device could run alongside a small computer for processing and inserting the data...
Flexible and fast deployable data acquisition system has been always demanded by tokamak facilities. This work proposes a full stack data acquisition, archive and access solution for J-TEXT based on Web technologies. This solution is based on a single unified software. This software can be configured into data acquisition software, data archiving server as well as data access and management...
The superconducting stellerator Wendelstein 7-X has successfully concluded its third operation phase in October 2018. The machine will see substantial changes during the next two years, when an actively cooled divertor will be installed, as well as many new diagnostic systems. The W7-X Control, Data Acquisition and Communication (CoDaC) group is responsible for the integration of all new...
This paper presents the KSTAR (Korea Superconducting Tokamak Advanced Research) real time framework for parallel streaming data processing framework (RT-ParaPro). RT-ParaPro is a framework used to develop programs that simultaneously process streaming data transmitted over a real-time network and send data over a network and archive them in real time. In most fusion experimental devices, each...
The KSTAR Quench Detection System (QDS) has been operated to protect the superconducting coil system of the KSTAR device in the last decade. The QDS discriminates a normal voltage of ~100 mV on NbTi or Nb3Sn Cable-in-Conduit Conductors (CICCs) in the event of quench, while the Poloidal Field (PF) coils are applied with voltages of up to some kV by pulsed operation of the Magnet...
The Wendelstein 7-X superconducting stellarator is a fusion experiment designed for processing of short plasma discharges in the range of some seconds up to long discharges up to 30min in a quasi-steady state operation mode. The first plasma experiment was conducted in December 2015. Since this first plasma experiment within three operational phases were successfully performed more than 100...
The safety related PLC in the central safety system (cSS) of W7-X with its corresponding periphery ensures occupational safety and the basic protection of investment. Because its reaction time in the range of some 100 ms is not sufficient to protect components in the plasma vessel from overloading by plasma heating (up to 14 MW), the fast interlock system (FIS) was installed. It can respond to...
A new database system for the JT-60SA tokamak [1] has been developed. This system meets the following requirements: to hold all the JT-60SA data and prevent loss of data, to be easily available the data to the researchers without knowing internal configuration and structure of the database, to manage revision of the data so that the stored data can be traced back to an older revision at any...
Wendelstein 7-X (W7-X) is a stellarator experiment located in Greifswald, Germany. In the first operational phases (OPs), the W7-X team has been already working on a variety of research topics with about 40 diagnostic systems in operation. In these OPs, many plasma discharges (50 per day/1000 per OP) with durations of up to 100 s were conducted, producing about 500 terabyte of experiment data....
With the increasing of data storage and data access in EAST experiment, standardized data access and user behavior monitoring become even more important. Therefore, a perfect EAST MDSplus logging system is required, and a mature log data management system is built on this basis. The EAST MDSplus log data management system architecture includes four parts: the log data collection layer, the...
Machine learning based disruption prediction method have exhibited good prediction performance with higher success rate, low false alarm rate and earlier warning time than physics based methods. One important thing pushed recent advances in machine learning field is high-quality training data. So a database with rich set of accurate disruption related labels is crucial to the development of a...
Successful reproduction of advanced tokamak scenarios in burning plasmas like ITER will strongly rely on sophisticated plasma control systems. Among the novel control physics challenges required to accomplish the control needed for scenario execution, the internal profile regulation plays a fundamental role [1]. The non-linear dynamics involved in current profile control are described by the...
The authors have been porting post data analysis systems used for the LHD project to the KSTAR project. The first one is AutoAna, or Automatic Analysis System. It is a system to manage programs to produce physical data for the LHD experiment. All the physical data for the LHD experiment is stored in the Kaiseki Server, or Analysis Server. Until the end of the fiscal year 2018, the Kaiseki...
Anomaly detection refers to the problem of finding patterns in data that do not conform to expected behavior. These off-normal patterns are often referred to as anomalies, outliers, discordant observations, or exceptions in different application domains. The importance of anomaly detection is due to the fact that anomalies in data frequently involves significant and critical information in...
Big data analytics deals with heterogeneous, complex and massive datasets to identify patterns that are hidden inside enormous volumes of data. ITER is expected to acquire more than 1 Tbyte of data per discharge. This amount of data comes from hundreds of thousands of signals acquired in each discharge. Signals can be time/amplitude series, temporal evolution of profiles and video-movies...
The energy-sweeping mode was recently used for measurement of the charge exchange flux energy distribution every 3-5ms via single-channel electrostatic neutral particle analyzer (NPA) in stellarator U-3M [1].The magnetic mass-separation (MS) part of NPA was omitted during these energy-sweeping measurements.The MS part is required for some experimental conditions in a case of presents of...
In modern fusion experiments, the remote data access has already come into wide use in both domestic and international research collaborations. SNET mutual data exchanging platform in Japan interconnects four fusion experimental sites, LHD, QUEST, GAMMA10, and TST-2, over 1 000 km distance and enables the remote collaborators access each site’s data seamlessly as if they were in local site....
MITICA is the prototype of the ITER full-size Heating Neutral Beam injector (HNB). It is being installed in the Neutral Beam Test Facility established at Consorzio RFX in Padova, Italy. The operation of MITICA requires the integrated collaboration of a large set of plant systems, including high-voltage power supply (-1MV / 60 A), radio frequency power supply (4 generators, 0.9 – 1. 1 MHz / 200...
This paper presents the KSTAR (Korea Superconducting Tokamak Advanced Research) real time framework for parallel streaming data processing framework (RT-ParaPro). RT-ParaPro is a framework used to develop programs that simultaneously process streaming data transmitted over a real-time network and send data over a network and archive them in real time. In most fusion experimental devices, each...
A new database system for the JT-60SA tokamak [1] has been developed. This system meets the following requirements: to hold all the JT-60SA data and prevent loss of data, to be easily available the data to the researchers without knowing internal configuration and structure of the database, to manage revision of the data so that the stored data can be traced back to an older revision at any...
Existing disruption predictor based on machine learning techniques, have good prediction performance but all these methods need large training datasets with many disruptions to develop successful predictors. Future machines are unlikely to provide enough disruption samples since they cause excessive machine damage and these models cannot extrapolate to machines other than it was trained on. In...
Advancements in data collection techniques call for the use of MDSplus not just as a centralized server, but running close to the data collection devices as well. To facilitate this, a set of Docker images are being developed to deploy miniature, self-contained installations of MDSplus. The goal being that every device could run alongside a small computer for processing and inserting the data...
With the increasing of data storage and data access in EAST experiment, standardized data access and user behavior monitoring become even more important. Therefore, a perfect EAST MDSplus logging system is required, and a mature log data management system is built on this basis. The EAST MDSplus log data management system architecture includes four parts: the log data collection layer, the...
The KSTAR Quench Detection System (QDS) has been operated to protect the superconducting coil system of the KSTAR device in the last decade. The QDS discriminates a normal voltage of ~100 mV on NbTi or Nb3Sn Cable-in-Conduit Conductors (CICCs) in the event of quench, while the Poloidal Field (PF) coils are applied with voltages of up to some kV by pulsed operation of the Magnet...
MDSplus is a software tool dedicated to data acquisition, storage and analysis used for complex scientific experiments. MDSplus has been used for data managment for fusion experiments for years, and this paper will demonstrate it can be used for a wide variety of systems as well. We will show how to set up a very simple experiment, manage data retrival, storage and consumtion using MDSplus and...
Like any advanced tokamak devices, high heat flux to the divertor target is always a crucial issue for EAST to operate in high performance and steady sate [1]. Advanced magnetic diverted configuration, like snowflake (SF) and X-divertor, is one of the attractive methods to spread the heat fluxes over divertor targets in tokamak because of enhanced scrape-off layer transport and an increased...
The safety related PLC in the central safety system (cSS) of W7-X with its corresponding periphery ensures occupational safety and the basic protection of investment. Because its reaction time in the range of some 100 ms is not sufficient to protect components in the plasma vessel from overloading by plasma heating (up to 14 MW), the fast interlock system (FIS) was installed. It can respond to...
From Tore Supra to WEST: Evolution of the CODAC infrastructure
A. Berne, B. Santraine, N. Ravenel, J. Colnel, G. Caulier, F. Leroux
CEA-IRFM, F-13108 Saint-Paul-Lez-Durance, France
Abstract
Since 1988, the Tore Supra limiter tokamak at CEA Cadarache has been in operation, and obtained the record of the longest plasma duration of 6 minutes 30 seconds and over 1000 MJ of energy injected and...
Thanks to their flexibility, FPGA-based Data Acquisition (DAQ) and processing systems are well suited to develop applications that are standard, modular, maintainable and scalable. There is currently a variety of FPGA-based solutions implementing DAQ systems and there are different approaches to design the hardware inside the FPGA. Each approach has its advantages and drawbacks, in terms of...
GLAST is a series of small spherical tokamaks with an insulating vacuum vessel of major and minor radius of 20 and 10 cm respectively (for GLAST III). It is installed in NTFP, Islamabad, Pakistan. The purpose of these experiments is to understand different aspects of tokamak operation such as startup phase and then sustaining tokamak plasma for a sufficiently long time. In case of a...
Across research disciplines, the size, complexity, and heterogeneity of data sets is growing rapidly. Large projects are often long-running collaborations between evolving groups of researchers. Integrating and documenting these large heterogeneous data collections is a requirement for these data to be exploited, and for them to retain their value and meaning over time. The traditional...
New fusion research experiments will generate massive experimental data. For example, ITER will have above one million of variables from control signals and diagnostic systems. Some of these variables will produce data during long pulse (about 30 minutes) experiments and other will generate data continuously. Just to have a clearer idea of the problem, ITER estimates more than 10 GBytes/second...
The integration of advanced control schemes is becoming more important as the development of fusion experiments progresses.
The ASDEX Upgrade discharge control system (DCS) is designed to be adaptable via configuration, no recompilation is necessary to change the behaviour of the control system.
In order to enable advanced control schemes the required information has to be available during...
Based on the deep learning method, this paper introduced a set of ELM real-time recognition system on HL-2A. The system uses 5200 shots data (about 241,900 data slices) for learning. After more than 70 adjustments, a 22-layer convolutional neural network is obtained. The network can recognize whether a 30ms data slice contains the ELM signal, After smoothing, the system can recognize the ELMy...
PPPL and Columbia University are together building a solution for analyzing rotating magnetohydrodynamic (MHD) mode measurements in real-time on KSTAR for use in new KSTAR Plasma Control System (PCS) algorithms supporting disruption prediction and avoidance research on KSTAR. The KSTAR PCS is based on the General Atomics (GA) PCS and uses the same software infrastructure with a Reflective...
The KSTAR has MSE (Motional Stark Effect) diagnostics devices for measurement of plasma current density distribution. Real-time MSE is an essential diagnostic for advanced control over the q-profile in tokamaks [1]. The KSTAR MSE diagnostic data measurement system measures and stores a total of 25 signals and 2 reference signals at a rate of 2MHz sample per second. The KSTAR has developed the...
The Wendelstein 7-X superconducting stellarator is a fusion experiment designed for processing of short plasma discharges in the range of some seconds up to long discharges up to 30min in a quasi-steady state operation mode. The first plasma experiment was conducted in December 2015. Since this first plasma experiment within three operational phases were successfully performed more than 100...
The co-ordination of many processes/threads across many machines is a task intrinsic to plant, acquisition and machine control for all sufficiently complicated experimental devices. Although Inter-Process-Communication protocols have been developed for many applications, following decades of Tokamak operations at the Swiss Plasma Center, we decided to ask what specific messages, specifically...
In order to increase the safety, it is more important than ever to generate a signal to turn off the device even when the abnormal situation occurs during the plasma discharge. KSTAR has built the Fast Interlock System (FIS) since achieving first plasma in 2008, and built and operated the 4th version of FIS which using NI c-RIO technology in 2018 [1].
We moved the safety related...
Fenix [1] is the ASDEX Upgrade (AUG) flight simulator based on the 1-D ASTRA transport code coupled with the 2-D SPIDER equilibrium solver [2] and Simulink (simulation platform from MATLAB). Fenix is designed to simulate, prior every discharge, the entire discharge starting from ramping the Toroidal Field coils (TF), plasma start-up, flat-top and ramp down and finishing with ramping down the...
Wendelstein 7-X (W7-X) is a stellarator experiment located in Greifswald, Germany. In the first operational phases (OPs), the W7-X team has been already working on a variety of research topics with about 40 diagnostic systems in operation. In these OPs, many plasma discharges (50 per day/1000 per OP) with durations of up to 100 s were conducted, producing about 500 terabyte of experiment data....
The usage of FPGA-based DAQ systems has been growing in instrumentation and control systems for Big Science experiments over the last years. The combination of flexibility and performance that FPGAs give to DAQ and processing systems for diagnostics is unrivaled. Moreover, the tasks for which FPGAs are used have been increasing in number and complexity, for instance, data acquisition,...
Thomson Scattering (TS) System is a diagnostic system to measure electron temperature and density profiles of tokamak plasma. TS Data Acquisition (DAQ) system converts analog optic signals to digital data in order to calculate the profiles. In this poster, we propose a design of architecture for GPU-based parallel computation to accelerate the diagnostic calculation with a large amount of TS...
ASDEX Upgrade (AUG) since many years is using a built to purpose FPGA based PCIe computer interface with fast serial interconnects to external DAQ (data acquisition) devices as in-house standard. The renewal of large physics measurement systems („diagnostics“) for the Mirnov probes, the Soft-X-Ray cameras and others have been successfully conducted as planned. These diagnostics have also...
The design and construction of first Egyptian inertial electrostatic confinement IEC fusion device has been studied [1]. It consists of 2.8 cm stainless steel cathode, 6.5 cm anode diameter with 10 cm diameter 20 cm height vacuum chamber. The operation of IEC experiments has concentrated on pulsed operation to achieve the high currents required to generate increased reactions rates. The...
A Motional Stark Effect (MSE) diagnosis system was developed to measure the plasma current density distribution in the KSTAR tokamak. Currently, the MSE diagnostic system performs data analysis by applying Fourier transform algorithm by using the IDL (Interactive Data Language) software after measurement and digital archiving. However, in order to realize advanced plasma control aiming at the...
The implementation of control algorithms for nuclear fusion requires a real-time environment to ensure the correct operation of the device. Although several alternatives have been used in the fusion community during the past decades, ITER has committed to develop a new generation real-time framework for control, the ITER Real-Time Framework (RTF). The ITER-RTF has been developed taking into...
Fast plasma boundary reconstruction is usually used for real-time control of tokamak plasma. In EAST experiment, the time consuming for boundary reconstruction should be within 1ms to meet the need of real-time control. Fast evolution of cameras in recent years has made them promising tools for diagnostics of Tokamak. The solution presented in this paper consists of a prototype of high-speed...
The standardization of device driver’s implementation in distributed control systems is essential to reduce the development and integration effort. Nowadays, there are multiple distributed control systems and high-level applications used in the scientific community. Due to the lack of standardization in the interfaces with the device drivers, it is required to integrate each hardware device...
Development of software for small- and medium-sized experimental setups and custom laboratory equipment differs from the software production for large-scale experiments or commercial applications. Everyday work of research group involves different types of jobs with equipment control and data acquisition ranging from manipulation with distinct parts of equipment to operation with complete...
Remote experiment with WEST tokamak in CEA Cadarache France from the ITER Remote Experiment Centre (REC) in Japan was successfully carried out on November 2018. The construction of the REC was carried out at the Fusion Energy Research Centre (IFERC) under the agreement between the Government of Japan and the European Atomic Energy Community for the joint implementation of the Broader Approach...
Russian Domestic Agency has nine plasma diagnostics Procurement Arrangements with ITER Organization (IO). Before integrated commissioning at IO Site, it is necessary to test these diagnostics with most of the interfacing systems connected. As the process can be long-lasting, remote means of access should be implemented. In addition, it will be useful to develop and test remote participation...
Each ITER discharge (30 minutes long) is expected to produce O(10**5) signals. This vast quantity of data must be stored and analyzed using computers with large storage capacity and fast processing units. Also, it is important to note that these powerful computers and data centers will be usually situated in remote locations from the scientists. Both access to data and some type of analysis...
Streamed data visualization is a new requirement for long lasting discharges and more in general for every long lasting related experiment, such as the ITER Neutral Beam test facility. A prerequisite for live visualization is the ability of the underlying data system to support streaming in data acquisition. Data streaming is supported in MDSplus, a widely adopted data system in fusion...
WEST is a full metallic environment tokamak, with an X-point divertor configuration. It is targeted at testing ITER like divertor prototypes made of actively cooled bulk tungsten units, in tokamak conditions during long pulse operation. Several partners around the world contribute by
providing various elements like parts of the divertor, ICRH antenna, and diagnostics, or by contributing to the...
Flexible and fast deployable data acquisition system has been always demanded by tokamak facilities. This work proposes a full stack data acquisition, archive and access solution for J-TEXT based on Web technologies. This solution is based on a single unified software. This software can be configured into data acquisition software, data archiving server as well as data access and management...
Thomson Scattering (TS) System is a diagnostic system to measure electron temperature and density profiles of tokamak plasma. TS Data Acquisition (DAQ) system converts analog optic signals to digital data in order to calculate the profiles. In this poster, we propose a design of architecture for GPU-based parallel computation to accelerate the diagnostic calculation with a large amount of TS...
Fast plasma boundary reconstruction is usually used for real-time control of tokamak plasma. In EAST experiment, the time consuming for boundary reconstruction should be within 1ms to meet the need of real-time control. Fast evolution of cameras in recent years has made them promising tools for diagnostics of Tokamak. The solution presented in this paper consists of a prototype of high-speed...
Development of software for small- and medium-sized experimental setups and custom laboratory equipment differs from the software production for large-scale experiments or commercial applications. Everyday work of research group involves different types of jobs with equipment control and data acquisition ranging from manipulation with distinct parts of equipment to operation with complete...
Each ITER discharge (30 minutes long) is expected to produce O(10**5) signals. This vast quantity of data must be stored and analyzed using computers with large storage capacity and fast processing units. Also, it is important to note that these powerful computers and data centers will be usually situated in remote locations from the scientists. Both access to data and some type of analysis...
The implementation of control algorithms for nuclear fusion requires a real-time environment to ensure the correct operation of the device. Although several alternatives have been used in the fusion community during the past decades, ITER has committed to develop a new generation real-time framework for control, the ITER Real-Time Framework (RTF). The ITER-RTF has been developed taking into...
The usage of FPGA-based DAQ systems has been growing in instrumentation and control systems for Big Science experiments over the last years. The combination of flexibility and performance that FPGAs give to DAQ and processing systems for diagnostics is unrivaled. Moreover, the tasks for which FPGAs are used have been increasing in number and complexity, for instance, data acquisition,...
A Motional Stark Effect (MSE) diagnosis system was developed to measure the plasma current density distribution in the KSTAR tokamak. Currently, the MSE diagnostic system performs data analysis by applying Fourier transform algorithm by using the IDL (Interactive Data Language) software after measurement and digital archiving. However, in order to realize advanced plasma control aiming at the...
The design and construction of first Egyptian inertial electrostatic confinement IEC fusion device has been studied [1]. It consists of 2.8 cm stainless steel cathode, 6.5 cm anode diameter with 10 cm diameter 20 cm height vacuum chamber. The operation of IEC experiments has concentrated on pulsed operation to achieve the high currents required to generate increased reactions rates. The...
ASDEX Upgrade (AUG) since many years is using a built to purpose FPGA based PCIe computer interface with fast serial interconnects to external DAQ (data acquisition) devices as in-house standard. The renewal of large physics measurement systems („diagnostics“) for the Mirnov probes, the Soft-X-Ray cameras and others have been successfully conducted as planned. These diagnostics have also...
Remote experiment with WEST tokamak in CEA Cadarache France from the ITER Remote Experiment Centre (REC) in Japan was successfully carried out on November 2018. The construction of the REC was carried out at the Fusion Energy Research Centre (IFERC) under the agreement between the Government of Japan and the European Atomic Energy Community for the joint implementation of the Broader Approach...
Russian Domestic Agency has nine plasma diagnostics Procurement Arrangements with ITER Organization (IO). Before integrated commissioning at IO Site, it is necessary to test these diagnostics with most of the interfacing systems connected. As the process can be long-lasting, remote means of access should be implemented. In addition, it will be useful to develop and test remote participation...
The standardization of device driver’s implementation in distributed control systems is essential to reduce the development and integration effort. Nowadays, there are multiple distributed control systems and high-level applications used in the scientific community. Due to the lack of standardization in the interfaces with the device drivers, it is required to integrate each hardware device...
The superconducting stellerator Wendelstein 7-X has successfully concluded its third operation phase in October 2018. The machine will see substantial changes during the next two years, when an actively cooled divertor will be installed, as well as many new diagnostic systems. The W7-X Control, Data Acquisition and Communication (CoDaC) group is responsible for the integration of all new...
WEST is a full metallic environment tokamak, with an X-point divertor configuration. It is
targeted at testing ITER like divertor prototypes made of actively cooled bulk tungsten units, in
tokamak conditions during long pulse operation. Several partners around the world contribute by
providing various elements like parts of the divertor, ICRH antenna, and diagnostics, or by
contributing to the...
Streamed data visualization is a new requirement for long lasting discharges and more in general for every long lasting related experiment, such as the ITER Neutral Beam test facility. A prerequisite for live visualization is the ability of the underlying data system to support streaming in data acquisition. Data streaming is supported in MDSplus, a widely adopted data system in fusion...
