111. A data transfer method for physics data of experimental fusion reactors using virtual disks
Kenjiro Yamanaka (National Institute of Informatics)
Data Storage and Retrieval, Distribution and Visulaization
Oral
118. A fully web based control system framework for fusion experiments
Wei Zheng (International Joint Research Laboratory of Magnetic Confinement Fusion and Plasma Physics, Huazhong University of Science and Technology)
Machine Control, Monitoring, Safety and Remote Manipulation
Oral
Fusion experiments like all large physics experiments requires orchestrating a large set or various subsystems. To make things more difficult is that comparing to accelerators, fusion experiments are far from finished, meaning they get upgrades and modifications all the time. So flexibility and interoperability are the main concerns. EPICS is mature in accelerator community and have been the... 116. A modern Infrastructure to manage shared diagnostic and very high amount of data
Julian COLNEL
Data Storage and Retrieval, Distribution and Visulaization
Oral
Measuring Soft X-Ray (SXR) emission in a tokamak gives access to plasma information such as impurity distribution, radiation emission, magnetic axis, etc. Current detectors used for SXR diagnostics, for instance semi-conductors, will not survive in the harsh environment of ITER caused by high neutron fluency. One solution is to use Gas Electron Multipliers (GEM) which measure X-ray emission... 126. A more flexible design for MDSplus Device drivers
Fernando Santoro (MIT/PSFC)
Data Acquisition and Signal Processing
Oral
The traditional approach to building MDSplus Device drivers is rigid and lacks the ability to meet changing needs. In this paper, we introduce a novel paradigm for Device driver development that allows the tree structure to dynamically change.This allows device drivers that can reconfigure to automatically reflect the hardware it represents, or a device that implements a variable number of... 101. Adaptive Anomaly Detection Disruption Prediction Starting from First Discharge
Mr Xinkun Ai (State Key Laboratory of Advanced Electromagnetic Technology, International Joint Research Laboratory of Magnetic Confinement Fusion and Plasma Physics, School of Electrical and Electronic Engineering, Huazhong University of Science and Technology)
Plasma disruption presents a significant challenge in tokamak fusion, especially in large-size devices like ITER, where it can cause severe damage and economic losses. Current disruption predictors mainly rely on data-driven methods, requiring extensive discharge data for training. However, future tokamaks require disruption prediction from the first shot, posing challenges of data scarcity... 103. AI/Machine Learning Enabled Advances with Real Time Control Validated on the DIII-D PCS
William Tang (Princeton Plasma Physics Laboratory)
William Tang`Heading`##The US goal (March, 2022) to deliver a Fusion Pilot Plant [1] has underscored urgency for accelerating the fusion energy development timeline. This will rely heavily on validated scientific and engineering advances driven by HPC together with advanced statistical methods featuring artificial intelligence/deep learning/machine... 91. CODIS:AN INTEGRATED CONTROL AND OPERATION SYSTEM FOR HL-3
Fan XIA (Southwestern Institute of Physics)
Machine Control, Monitoring, Safety and Remote Manipulation
Poster
CODIS(Control Operation Data Intelligent System) has being developed for the control and operation of HL-3 and other nuclear fusion experimental device. Its purpose is to integrate all people and all subsystems involved in the fusion experimental device into a unified system. The entire system is divided into three layers, namely the personnel function interface layer, the CODIS Core layer,... 137. Conceptual design of ELM control coils for the TCABR tokamak
Felipe Salvador (Institute of Physics of University of São Paulo)
Special Session for Physics Topics
Poster
An upgrade of the TCABR tokamak ($R_0 = 0.62$ m, $a \leq 0.18$ m, $I_p \leq 120$ kA and $B_0 \leq 1.1$ T) is being designed to enable the generation of a well controlled environment to assess the impact of resonant magnetic perturbation (RMP) fields on edge localised modes (ELMs). This impact can be investigated over a broad range of (i) plasma shapes, (ii) RMP coil geometries and (iii)... 133. Control, Data Acquisition and Communication at W7-X for the 2023/24 campaign (OP2.2)
Axel Winter (Max Planck Institut für Plasmaphysik)
Machine Control, Monitoring, Safety and Remote Manipulation
Oral
The superconducting stellarator W7-X underwent a major overhaul between 2018-2022 with the installation of an actively cooled divertor and inner wall. The CoDaC System also received a significant overhaul and expansion. The central safety system was completely re-implemented with the lessons learned from previous operation phases and the new requirements of OP2.1. The protection of the new... 72. Description of magnetic field lines in fusion plasmas by the Hamiltonian formalism
Michele Mugnaine (Instituto de Física da Universidade de São Paulo)
Special Session for Physics Topics
Poster
In tokamaks, the superposition of a toroidal magnetic field, due to external coils around the entire torus, and the poloidal field, generated by the plasma current itself, is responsible for the plasma confinement. An interesting situation is when the magnetic field is time-independent, as is the case in MHD equilibrium configurations. For a symmetric plasma equilibrium configuration with an... 68. Design and Implementation of Fast Real Time Signal Processing System for different feedback control applications for Tokamak Experiments
Mr PRAVEENLAL EDAPPALA (Institute for Plasma Research)
Plasma Control and Simulation
Poster
A fast real-time signal processing system based on a digital signal microcontroller has been designed and implemented for various feedback control applications In Aditya-Upgrade Tokamak and associated experiments. The hardware design has a 32-bit microcontroller with a single precision floating point engine, in which a mathematical calculation can be done in less than 20ns. The other key... 77. Design and Preliminary Realization of Virtual Installation based on Binocular Vision
Ms dan Li (Hefei Institutes of Physical Science)
Data Storage and Retrieval, Distribution and Visulaization
Oral
Currently operating fusion devices and future fusion reactors share common features such as complex systems, limited space, expensive components, and some nuclear-related aspects. Consequently, traditional component installation or maintenance is inefficient. The immersive virtual installation achieved on EAST provides researchers with functionalities such as scheme discussions and... 87. Design of Data Management for New Plasma Control System
Jianqiu Zhu (Institute Of Plasma Physics Chinese Academy Of Sciences)
Plasma Control and Simulation
Oral
The Plasma Control System (PCS) serves as the central control system responsible for operating the tokamak and controlling the plasma therein.A new framework of PCS for high-performance steady-state operation is designed.It is built based on component modularity, providing the operational environment for components, data management model and interfaces to external systems.A meticulously... 100. Developing JET Gas Controllers with Uncertainty Quantified Deep Learning Models for Plasma Control
Hudson Baker (UK Atomic Energy Authority)
JET pulses are regularly disrupted by the iterative process of tuning the gas controllers. Current gas calibration methods cannot accommodate the time-varying parameters of the gas system, which leads to poor repeatability of experiments. Therefore, there is a need for improved gas control algorithms. Developing these algorithms requires a significant amount of testing to evaluate performance.... 114. Development of Control and Data Acquisition systems for neutron tomography
waleed Abd El bar (Egyptian Atomic Energy Authority (AEA), ETRR-2, Egypt.)
Data Acquisition and Signal Processing
Poster
![enter image description here][1]Neutron tomography system offers two key advantages over conventional sensing systems. Firstly, process tomography systems provide information about 2D or 3D distributions of the variables of interest with looks inside the sample without penetrating. Secondly, tomography is a very powerful technique for nondestructive evaluation of heavy industrial components... 97. Disruption prediction based on disruption budget consumption on J-TEXT
Yu Zhong (Huazhong University of Science and Technology)
The successful operation of tokamak devices, such as ITER, depends on effectively managing disruptive events. These occurrences can abruptly terminate discharges and trigger thermal and current quenches, posing severe threats to device structural integrity. Thus, precise disruption budgeting is essential to achieve operational objectives.Disruption damage is quantified through a disruption... 102. Distributed editing of experiment programs at Wendelstein 7-X
Anett Spring (Max Planck Institute for Plasma Physics)
Plasma Control and Simulation
Poster
Wendelstein 7-X – as the world’s largest stellarator-type fusion device – has been going successfully through its first operation phases showing reliable operation assisted by the W7-X Segment Control and experiment-planning framework. During the upgrade phase for the full machine extent, not only the actively cooled divertor and first wall are being installed, but also a list of new... 78. EAST Integrated Data Access System Based On Spring Cloud
Mr Feng Wang (Hefei Institutes of Physical Science, Chinese Academy of Sciences)
Data Storage and Retrieval, Distribution and Visulaization
Poster
The experimental data generated by EAST during operation includes different types such as operation logs, control data, engineering data, diagnostic data and etc. Combined with visual operation requirements and data structures, multiple data service systems are established based on a single architecture. As the experiment continues to run, the scale of experimental data, system access load,... 123. End-to-end in-pulse data analysis at ITER: from magnetics measurements to live display
Paulo Abreu (ITER Organization)
Data Storage and Retrieval, Distribution and Visulaization
Oral
Interpreting diagnostic data promptly after it is recorded remains a crucial aspect of modern tokamaks where rapid evaluation of plasma performance during a pulse is essential for operational efficiency and the implementation of the scientific programme. In this work, we present recent progress in developing a demonstrator for an in-pulse processing workflow for ITER, from simulated magnetic... 94. Enhancing Fusion Research with TokSearch: Updates and Integration into the Fusion Data Platform
Brian Sammuli (General Atomics)
Data Storage and Retrieval, Distribution and Visulaization
Oral
The rapidly evolving field of fusion research demands sophisticated data processing and management tools to handle the immense volumes of experimental data generated by tokamak operations. In response to these needs, TokSearch, a fusion data processing framework developed by General Atomics and recently open-sourced, has undergone significant upgrades to better serve the fusion research... 71. Enhancing Nuclear Fusion Reactor Operation through Machine Control and Monitoring
Mr Ahmed Salman (Egyptian atomic energy authority)
Machine Control, Monitoring, Safety and Remote Manipulation
Poster
Nuclear fusion has long been pursued as a promising source of clean and abundant energy. The successful operation of a nuclear fusion reactor relies on precise control and monitoring of various parameters to ensure safe and efficient operation. In this research paper, we present an overview of the machine control and monitoring systems developed for nuclear fusion reactors. The machine control... 95. Enhancing Operational Safety: The NSTX-U Shorted Turn Protection (STP) System
Domenica Corona Rivera (Princeton Plasma Physics Laboratory (PPPL))
Machine Control, Monitoring, Safety and Remote Manipulation
Oral
The NSTX-U Shorted Turn Protection (STP) system is an essential safety feature of the NSTX-U tokamak, designed to safeguard its coils during experimental operations. With the upcoming upgrade of the NSTX-U facility, the implementation of the STP system becomes even more critical in ensuring the reliability and safety of research activities.The development of the STP system was prompted by... 81. Fast control of plasma vertical displacement based on robust adversarial reinforcement learning
Dr Binnuo Liu (Institute of Plasma Physics, Chinese Academy of Sciences)
Plasma with elongated configuration has the advantage of higher discharge parameters while at the cost of vertical displacement instability. Once the vertical displacement is out of control, it will inevitably lead to a major disruption, causing great damage to the device, which will have unacceptable consequences if it occurs on ITER. Therefore, active control of vertical displacement is... 98. Fusion Data Platform for HL-3
Xiang Sun (Southwestern Institute of Physics)
Data Storage and Retrieval, Distribution and Visulaization
Poster
The HL-3 Fusion Big Data Platform is a system developed on the open-source Hadoop platform specifically tailored for processing tokamak experimental data. Unlike traditional big data platforms dealing with service data periodically, massive amounts of data are generated by tokamak experiments typically within seconds or minutes. And these data are mostly transmitted and stored in binary... 76. Hamiltonian Map for Guiding Center Orbits in Tokamak Plasmas
Lucas Amaral (University of São Paulo)
Special Session for Physics Topics
Poster
One of the primary challenges associated with plasma confinement in tokamaks is the escape of energetic particles at the plasma edge. One approach to managing the flux of these particles is modifying the electric and magnetic fields in this region, thereby establishing conditions that reduce transport. To investigate which configurations of electric and magnetic fields create transport... 92. Identification of MHD modes on EAST using a deep learning framework
Prof. biao shen (Institute of plasma physics, Chinese Academy of Sciences)
In Tokamak plasma, The instability of magnetohydrodynamic(MHD) severely limits the improvement of plasma parameters and may even lead to plasma disruption events, thereby threatening the safety of device components. The identification of MHD modes is crucial for the study and control of MHD instabilities. Traditional MHD mode recognition methods mostly use the raw information of... 84. Implementation of High Speed Data Acquisition at DIII-D
Austin Keller (DIII-D National Fusion Facility, General Atomics)
Data Acquisition and Signal Processing
Poster
Research at the DIII-D National Fusion Facility in San Diego focuses on short pulse plasma discharges that specialize on various shaping profiles. High speed data collection is a critical component for the operation of many of DIII-D’s diagnostics. This is fundamental for capturing high resolution data used in experimental data analysis. Differing techniques enable the plasma control system... 70. Indigenization and development of frequency source, data acquisition and IF section for FMCW Reflectometry at IPR
Mr Vishnukumar Chaudhari (Institute for plasma research)
Plasma Control and Simulation
Poster
Aditya-U has two operational reflectometers in the K (18-28 GHz) and Ka (26-40 GHz) frequency bands for measuring the density profile. An FPGA-based card has been developed indigenously to linearize the microwave frequency sources. This card generates an arbitrary voltage ramp to drive the oscillators and synchronize them with the tokamak control. Further, this FPGA hardware has been used to... 83. Indoor radon and ambient equivalent dose measurements using a locally manufactured low-cost smart electronic device and validation with reference instruments
JACOB MBARNDOUKA TAAMTE (Research Centre for Nuclear Science and Technology, Institute of Geological and Mining Research, P.O. Box 4110 Yaoundé, Yaoundé, Cameroon)
Data Acquisition and Signal Processing
Oral
Conventional equipment intended for environmental monitoring are excessively expensive, heavy and difficult to implement. Thanks to the digital revolution and IoT technology, it is possible to realize smart and inexpensive devices with wireless data transmission to a remote computer. This work reports the realization of an improved version of low-cost intelligent electronic device for... 130. Information theory applied to numerical simulations of resistive drift-wave turbulent in tokamak plasmas
Mrs Sarah Gomes da Silva Paes da Costa (University of Brasilia)
Special Session for Physics Topics
Poster
Turbulence dominates the radial transport at the edge region of tokamak plasmas, reducing magnetic confinement in fusion experiments, and its control remains a challenge in physics and engineering. Information theory can provide useful tools to quantify the degree of order/disorder of turbulent fluids and plasmas. In this work we analyze numerical simulations of a simplified nonlinear model of... 119. Investigating the role of the edge radial electric field in the formation of shearless transport barriers in tokamaks
Leonardo Antonio Osorio-Quiroga
Special Session for Physics Topics
Poster
An $\mathbf{E}\times\mathbf{B}$ drift wave transport model was implemented to investigate chaotic transport at the edge of magnetised plasmas in tokamaks. We show that pronounced reversed-shear radial electric field profiles at the plasma edge can create shearless transport barriers (STBs) which confined most of the particle orbits inside the plasma. These barriers are related to the presence... 128. JET CODAS The Final Status
Dr John Waterhouse (UKAEA)
Machine Control, Monitoring, Safety and Remote Manipulation
Oral
The JET Control and Data Acquisition System has stood the test of time and seen us through to the end of JET Operations in 2023. The system architecture has remained largely un-changed over the last decade or so although many new diagnostics and control systems have been added and the volume of data collected has grown massively. CAMAC remains at the heart of the system, particularly for... 127. JET Plasma Control System Upgrade using MARTe2
Adam Stephen (UKAEA)
Plasma Control and Simulation
Oral
JET real-time plasma control has been delivered with a heterogeneous collection of control systems linked by a dedicated low-jitter, low-latency network. To provide a high degree of flexibility in tuning plasma control algorithms to experimental requirements, the Real-Time Central Controller (RTCC) has been available since 1997. RTCC provides a sandboxed execution environment where... 129. Mapping Alcator C-Mod data into IMAS using the UDA JSON mapping plugin
Jonathan Hollocombe (UKAEA)
Data Storage and Retrieval, Distribution and Visulaization
Oral
To facilitate the interoperability and reusability of analysis codes, and general interoperability of data from different fusion experiments, work has been undertaken to map the data from these experiments into the IMAS (ITER Integrated Modelling and Analysis Suite) data model[1]. This mapping can be done on an adhoc basis with the generated IDSs being then made available locally or via remote... 96. MDSplus version 8.0: The Path to Long Node Names
Mark Winkel (MIT Plasma Science and Fusion Center)
Data Storage and Retrieval, Distribution and Visulaization
Oral
MDSplus version 8.0 introduces 63-byte node names (in preparation for UTF-8 support). Which means that signals can now have meaningful names, including the long names used in the IMAS / OMAS dictionaries. This presentation describes the current state of the version 8.0 pre-release, possible enhancements, and how to obtain a copy of the software.Some preliminary uses of version 8.0 will... 136. MDSplusML - Optimizations for data access to facilitate machine learning pipelines
Joshua Stillerman (MIT Plasma Science and Fusion Center)
The MDSplus[1][2] data management system is widely used in the magnetic fusion energy research community for data storage, management, and remote access. The system provides data access through a vector based, interpreter API. It was developed and optimized for rapid single shot analyses. Machine Learning applications require data from large numbers of shots and potentially from different... 86. Model-based vertical position control design and optimization for CFETR tokamak
Yuehang Wang (ASIPP)
Plasma Control and Simulation
Oral
The vertical displacement instability is an inherent characteristic of tokamaks using elongated configurations. The uncontrolled growth of this instability will lead to plasma disruption, resulting in discharge termination and damage to the device. Therefore, it is necessary to control this instability. Due to the shielding effect of the vacuum vessel on external coils, full superconducting... 135. Modeling separatrix splitting and magnetic footprints in TCABR
Jose Roberto Fernandes Junior (Institute of Physics - University of São Paulo)
Special Session for Physics Topics
Poster
Plasma instabilities are still a concern when thermonuclear conditions are approached as they can impose severe constraints on the maximum achievable plasma performance. When operating in the so-called high confinement mode (H-mode) a very steep plasma pressure profile is formed in the plasma edge, which leads to repetitive instabilities known as edge localized modes (ELMs). The crash of these... 74. Modeling, design and implementation of multi input and multi-output control system for plasma position in Damavand tokamak
Hossein rasouli
Plasma Control and Simulation
Poster
In this work, a nonlinear model is introduced to determine the vertical and horizontal position model of the plasma column in Damavand tokamak. Using this model as a simulator, a multi-input and multi-output (MIMO) controller has been designed. Also this controller is implemented on digital signal processor (DSP) control system. In the first stage, a nonlinear model is identified for plasma... Simon Fischer (Max Planck Institute for Plasma Physics, Greifswald, Germany)
Data Storage and Retrieval, Distribution and Visulaization
Oral
The Wendelstein 7-X fusion experiment is an optimized stellarator, equipped with more than 60 different diagnostic systems. Many of those diagnostics comprise optical and/or infrared spectrum sensor arrays of various technologies (cameras). In order to enable full compliance with accepted scientific methods, all data generated by these systems (during experiments) are stored in the W7-X... 75. Onset of multiple transport barriers in tokamak configurations
Gabriel Grime (University of São Paulo)
Special Session for Physics Topics
Poster
For certain discharge configurations in tokamaks, transport barriers reduce particle transport, thereby improving plasma confinement. In this context, a model has been applied to describe turbulent transport caused by drift waves at the plasma edge, attributing this transport to chaotic orbits originated from $\textbf{E}\times\textbf{B}$ drift. In the present work, we use this model to... 134. Operation and Remote Collaboration Tools in view of the ITER Neutral Beam Test Facility Experimental Campaigns
Dr Nuno Cruz (Instituto de Plasmas e Fusão Nuclear, Instituto Superior Técnico, Universidade de Lisboa)
Data Storage and Retrieval, Distribution and Visulaization
Oral
The ITER Neutral Beam Test Facility (NBTF) serves as a crucial testing ground for the development and validation of neutral beam injection systems essential for ITER's fusion power plant. Two experimental campaigns, SPIDER and MITICA, are conducted within the NBTF. SPIDER (Source for Production of Ion of Deuterium Extracted from Rf Plasma) focuses on the development and optimization of the ion... 108. Plasma Boundary Shape Reconstruction Using Visible Spectroscopy Diagnosis on EAST Tokamak
Mr ming chen
Data Acquisition and Signal Processing
Oral
Plasma shape control is a prerequisite for the stable operation of tokamak devices. Future fusion reactors anticipated to have longer burn length and higher discharge performance, current shape reconstruction methods based on magnetic diagnostics will encounter challenges related to signal drift and probe maintenance.Hence, a plasma boundary shape reconstruction system utilizing visible... 85. Plasma control with artificial intelligence on EAST
Bingjia Xiao (Institute of Plasma Physics, Chinese Academy of Sciences)
Robust control of tokamak plasma is still one of the most challenges for a fusion reactor due to the complicated plasma dynamics together with its response with complicated structures and actuators and the extreme control requirements. In recent years, artificial intelligence showed its great potential in predication of plasma states and in control of plasma equilibrium. On EAST, all disrupted... 82. Plasma instability analysis and control in Texas Helimak
Arnold Alonso Alvarez (University of São Paulo)
Data Acquisition and Signal Processing
Poster
Texas Helimak is a toroidal magnetic confinement device in a configuration known as Simple Magnetic Tori (SMT). Its simple geometry and wide radial region provide plasma density and temperature conditions analogous to those in the edge and Scrape-Off Layer (SOL) of tokamak devices. This allows for the evaluation of different mechanisms for effectively controlling turbulence. One such... 113. Plasma Instability Events Identification and Disruption Prediction in EAST Based on Multi-Task Learning
yunhu Jia (中国科学院合肥物质科学研究院等离子体物理研究所)
High-performance disruption prediction and instability event identification are crucial for tokamak plasma operation. Given the intrinsic correlation between plasma disruptions and their precursor instability events, this study introduces a multi-task learning-based integrated model that concurrently processes both tasks. The model identifies three key instability events—Edge Localized Modes... 90. Plasma optical boundary detection based on instance segmentation
Qirui Zhang
During long pulse steady-state discharge, the position and shape of plasma reconstructed by the EFIT code may produce significant errors due to factors such as integrator drift and local magnetic field changes, which in turn affect discharge stability. However, optical based boundary reconstruction signals are not affected by the complex electromagnetic environment within the Tokamak. The use... 112. Progress of "Plasma and Fusion Cloud" Research Data Ecosystem Orienting "Open Science"
Dr Hideya Nakanishi (National Institute for Fusion Science)
Data Storage and Retrieval, Distribution and Visulaization
Oral
A new cloud platform to realize plasma/fusion experimental data ecosystem, named "Plasma and Fusion Cloud," has been technically verified on some fundamental issues. Enormous amount of diagnostic data require a high-performance computing (HPC) platform not only for the LHD physics data analyses and also for the next-generation experiments, such as ITER and JT-60SA. Performance evaluation have... 115. Progress with Remote Participation Tools in ITER Control System
Mr Denis Stepanov (ITER Organization)
Machine Control, Monitoring, Safety and Remote Manipulation
Oral
This contribution gives an update on the progress of remote participation in the ITER conventional control system (CODAC) since the previous IAEA technical meeting in 2021. Six out of seven ITER partners have been connected 24x7, two of them using high-performance Open Systems Interconnection (OSI) level 2 virtual private networks. A new, high-bandwidth network connection node has been... 89. Prototype design of logic testing controller based on FPGA for interlock system
Zuchao ZHANG
Machine Control, Monitoring, Safety and Remote Manipulation
Oral
The national project of experimental advanced superconducting tokamak (EAST) is an important part of the fusion development stratagem of China, which has fully superconducting tokamak with a non-circle cross-section of the vacuum vessel and the active cooling plasma-facing components. The safety and interlock system (SIS) is in charge of the supervision and control of all the EAST components... 109. Radial profiles of turbulence level in Texas Helimak
Giuseppe Silva (University of São Paulo)
Special Session for Physics Topics
Poster
My masters dissertation, which titles this work, had the main goal was to reproduce existing results regarding plasma radial density profiles in the Texas Helimak device and expand such results for data not analyzed before.In the Texas Helimak, a set of 96 Langmuir probes connected to a digitizer device of 500 kHz of sampling frequency register the data of the plasma's ionic saturation... 122. Real-time estimation of line-averaged plasma density on EAST using LightGBM
Yucheng Wang
The reliability of the plasma density measurement is crucial for plasma densitycontrol in tokamak. Currently, the density feedback system in EAST uses lineaveraged density from either the Hydrogen Cyanide (HCN) laser interferometeror the polarimeter-interferometer (POINT) diagnostic system. However, insufficient laser energy or noise interference can lead to erroneous density... 88. Reconstruction of plasma equilibrium using physics-informed neural network on EAST
Wenbin Liao (Institute Of Plasma Physics, Chinese Academy Of Sciences)
The traditional algorithm currently used for plasma equilibrium reconstruction in tokamaks assumes a plasma current profile in a certain polynomial form (usually 2nd or 3rd order) or a tension spline function and performs a least square fitting to the diagnostic data under the model given by the Grad-Shafranov equation [1]. The physics-informed neural network (PINN) integrates measurement data... 120. Revealing stickiness in a field line map using recurrence analysis
Leonardo Souza (Institute of Physics, University of São Paulo)
Special Session for Physics Topics
Poster
In fusion plasmas, the stickiness effect manifests as the prolonged trapping of magnetic field lines in a specific region for many toroidal turns, significantly impacting plasma transport. We utilize a concept based on recurrence plots, which unveils the presence of a hierarchical structure of islands around islands where chaotic orbits become trapped. This analysis is performed on a... 131. Role of Lagrangian vortices in numerical simulations of resistive drift-wave turbulence in tokamak plasmas
Dr Rodrigo A. Miranda (University of Brasilia)
Special Session for Physics Topics
Oral
We perform numerical simulations of a simplified nonlinear model that describes drift-wave turbulence in tokamak plasmas. By changing the value of a control parameter related to adiabaticity, the numerical solutions display a transition from a turbulent regime, into a regime dominated by zonal flows, in which turbulence and radial transport are greatly reduced. This transition can be regarded... 125. Russian FusionSpace.RU
Mr Sergey Portone (Project Center ITER)
Data Storage and Retrieval, Distribution and Visulaization
Oral
Currently, a large amount of knowledge has been accumulated in the field of Fusion Research. Long-term experience of several generations of scientists disposes in accumulated experimental databases, theoretical works, mathematical models, codes, literature, technical documentation etc.Modern information technologies make it possible to consolidate such databases on a single information... 124. Scalable Real-time Framework Enabling Machine Learning Based Plasma Control
Keith Erickson (PPPL)
Plasma Control and Simulation
Oral
The Princeton Plasma Physics Lab (PPPL) has demonstrated the effectiveness of a scalable real-time framework that enables plasma control system (PCS) algorithms to utilize heterogeneous inputs at both millisecond and microsecond speeds. Current developments target real-time plasma control algorithm challenges by combining new hardware technologies and proven software techniques with new... 79. Shearless barrier in the multiple spatial modes drift wave model
Luis F. B. Souza (Institute of Physics, University of São Paulo)
Special Session for Physics Topics
Poster
A model based on the theoretical framework of drift wave turbulence is utilized to investigate anomalous transport in plasma magnetic confinement experiments. The drift wave model incorporates a perturbation consisting of an infinite number of spatial modes and a broad spectrum of frequencies, which is presented in such a way that it provides a Hamiltonian approximation, leading to a... 121. SPARC Instrumentation and Control System Status and Plans
William Davis
Machine Control, Monitoring, Safety and Remote Manipulation
Oral
138. Structural analyses of the in-vessel ELM control coils of the TCABR tokamak
Andre Bouzan (Polytechnic School of the University of São Paulo)
Plasma Control and Simulation
Poster
An upgrade of the TCABR tokamak ($R_0=0.62$ m, $a=0.18$ m, $I_p \leq 120$ kA e $B_0\leq1.1$ T) is being carried out to allow for studies of the impact of resonant magnetic perturbation (RMP) fields on plasma instabilities known as edge localized modes (ELMs). ELMs may impinge heat fluxes on the surface of plasma-facing components that are typically well above the values supported by the... 117. The Control and Data Acquisition System of the DTT experiment
Gabriele Manduchi
Data Acquisition and Signal Processing
Oral
DTT, Divertor Tokamak Test facility, is currently under construction at the Frascati ENEA Research Center. Its aim is to explore alternative solutions for the extraction of the heat generated by the fusion process. Its Control and Data Acquisition System (CODAS) will (1) orchestrate and synchronize all the DTT systems during Plasma operation and maintenance; (2) acquire data from the... 80. The design and implementation of a new plasma control system
Prof. Qiping Yuan (Institute of Plasma Physics, Chinese Academy of Sciences)
Plasma Control and Simulation
Oral
For present tokamaks and future fusion reactors, the control of plasma initiation, shaping, heating, stabilization, and safe termination of discharges is required. In order to integrate various control functions and meet the requirements of safe and steady-state operation of the device, the design and implementation of the plasma control system (PCS) infrastructure have been completed. A... 106. The new CODAS implementation for the TCABR tokamak upgrade
Wanderley Pires de Sá (Institute of Physics of University of São Paulo)
Plasma Control and Simulation
Oral
An update is being carried out on the TCABR tokamak (small tokamak, with R0 = 0.62 m and a = 0.2 m) in operation at the Physics Institute of the University of São Paulo, Brazil. This upgrade consists of the installation of (i) graphite tiles to fully cover the inner surface of the vacuum vessel wall, (ii) new poloidal field (PF) coils to allow the generation of diverse plasma configurations,... 93. The new progress of detachment feedback control by N2 seeding under H-mode long-pulse plasma on EAST
Kai Wu (Institute of Plasma Physics, Hefei institutes of physical sciences, Chinese academy of sciences)
Plasma Control and Simulation
Oral
The plasma facing materials(PFCs), especially the divertor targets, are facing the continuous excessive heat strike issue, which will be more severe in the future fusion reactors like ITER. Generating the stable detached plasma is an acknowledged way to solve this problem and has been applied in the different tokamaks. On EAST, the ITER-like tungsten divertor and long-pulse discharge(over... 132. THE TRIGGERING OF NEOCLASSICAL TEARING MODES BY SAWTEETH IN THE TCABR TOKAMAK
Gustavo Antonio Pires Vaccani (ITA)
Special Session for Physics Topics
Poster
This work addresses a pending issue in developing thermonuclear fusion: the triggering of neoclassical tearing modes (NTMs) by sawteeth (ST) in tokamak plasmas. Although ST and NTMs have been intensively investigated in recent decades, a quantitative and validated theory of ST-triggered NTMs is yet to be developed. Specifically, it is not possible to reliably predict the triggering of NTMs in... 105. Time Correlated Bursts in the Texas Helimak
David Chang
Special Session for Physics Topics
Poster
The turbulence in magnetically confined plasmas exhibits certain universal properties with the presence of coherent high-density structures, generically called bursts. These structures propagate convectively and, therefore, have a relevant impact on the plasma confinement. In the classical Stochastic Pulse Train Model (SPTM), it is considered that bursts appear randomly, therefore, the... 73. Towards an Analysis-Ready, Cloud-Optimised service for FAIR fusion data
Mr Samuel Jackson (UKAEA)
Data Storage and Retrieval, Distribution and Visulaization
Oral
We present our work to improve data accessibility and performance for data-intensive tasks within the fusion research community. Our primary goal is to develop services that facilitate efficient access for data-intensive applications while ensuring compliance with FAIR principles [1], as well as adoption of interoperable tools, methods and standards. The major outcome of our work is the... 107. Updating the Build, Test, and Deploy systems for MDSplus
Stephen Lane-Walsh (MIT)
Data Acquisition and Signal Processing
Oral
In order to better support development efforts on MDSplus, we needed to improve the Continuous-Integration/Continuous-Deployment (CI/CD) systems building MDSplus. To that end, we have created a new Jenkins server, utilizing the new scriptable Jenkinsfile method and modern security principles. Additionally, we have moved off of autotools, and on to CMake for our build system. Existing tooling... 99. Using Continuous Integration in the development and verification of a new central controller for JET
Edward Jones (User)
Next Steps/new Fusion devices technologies: Challenges and Opportunities
Oral
In the final year of JET’s operation new requirements were requested which were not possible with the current central control mechanism used in plasma control operations. The new requirements provided us with a justification to replace the system entirely to expand its operational capability and improve the user experience and processes. Given the nature of the system being replaced, it was... 110. “Plasma and Fusion Cloud” Data Analysis Environment
Masahiko Emoto (National Institute for Fusion Science)
Data Storage and Retrieval, Distribution and Visulaization
Poster
At the National Institute for Fusion Science (NIFS), “Plasma and Fusion Cloud” concept is currently underway. This concept is aims to establish a data analysis environment not only fusion plasma experiment, but other fields that transcends the boundaries of disciplines among universities in Japan, promoting the reuse of results such as experimental data obtained from existing experiments and... 