Nuclear Fusion最新文献

{"title":"Overview of physics results from the ADITYA-U tokamak and future experiments","authors":"R. Tanna, Joydeep Ghosh, K. Jadeja, Rohit Kumar, S. Aich, Kaushal Patel, H. Raj, Kaushlender Singh, S. Dolui, K. Shah, S. Patel, N. Yadava, T. Macwan, Abha Kanik, Ankit Kumar, Bharat Hegde, Ashok Kumar Kumawat, Ananya Kundu, Ramesh Joshi, D. Sharma, Ankit B Patel, Laxmikanta Pradhan, Kalpesh Galodiya, S. Pandya, Soumitra Banerjee, Injamul Hoque, Komal Yadav, M. Chowdhuri, R. Manchanda, N. Ramaiya, R. Dey, G. Shukla, Dipexa Modi, V. Sharma, Aman Gauttam, M. Makwana, K. S. Shah, Shivam Gupta, Supriya Nair, S. Purohit, U. Nagora, A. Adhiya, K. Patel, K. Asudani, S. Jha, D. Kumawat, S. Pandya, V. Siju, Praveenlal E V, B. Arambhadiya, M. Shah, P. Gautam, V. Raulji, Praveena Shukla, Abhijeet Kumar, Mitesh Patel, R. Rajpal, Manisha Bhandarkar, I. Mansuri, Kirti Mahajan, Kishore Mishra, Sunil Kumar, B. Shukla, J. Kumar, P. K. Sharma, Snehlata Aggarwal, Kumar Ajay, Manoj Kumar Gupta, S. K. Pathak, P. Chattopadhyay, D. Raju, Someswar Dutta, S. Pahari, N. Bisai, Chetna Chauhan, Y. Saxena, A. Sen, R. Pal, Shashank Ch","doi":"10.1088/1741-4326/ad3c50","DOIUrl":"https://doi.org/10.1088/1741-4326/ad3c50","url":null,"abstract":"\u0000 The ADITYA Upgrade (ADITYA-U), a medium-sized (R_0=75 cm,a=25 cm) conventional tokamak facility in India, has been consistently producing experiments findings by using circular and shaped-plasmas. Recognizing the plasma parameters aligning closely with the design parameters of circular limited plasmas, ADITYA-U shifted its focus toward exploring the operational regime for experimentation on saw-tooth and MHD phenomena. Moreover, ADITYA-U has made consistent advancements toward conducting preliminary plasma shaping experiments through the activation of top and bottom divertor coils utilizing hydrogen as well as deuterium fuels. Confinement is improved by a factor of ~ 1.5 in D_2 plasmas when compared to H_2 plasmas of ADITYA-U. Further, ADITYA-U operations emphasize preventing disruptions and runaway electrons (REs) to ensure safe operations for future fusion devices. Significant suppression of REs has been achieved in ADITYA-U with the application of pulsed localized vertical magnetic field (LVF) perturbation, thereby establishing the technique's independence from the tokamak device. The successful RE mitigation requires a critical threshold of LVF pulse magnitude, which is approximately 1% of the toroidal magnetic field, and a minimum duration of ~ 5 ms. Apart from this, several novel findings have been achieved in the ADITYA-U experiments, including the modification of sawtooth duration through gas-puff, the emergence of MHD-induced GAM-like oscillations, the propagation of fast heat pulses induced by MHD activity, the control of RE dynamics through Gas-puffs, the propagation of pinch-driven cold-pulses, the transport and core accumulations of argon impurities, the mass dependency of plasma toroidal rotation and the detection of “RICE” scaling, as well as the characterization of edge plasma using wall conditioning methods, such as glow discharge cleaning using a combination of Ar-H2 mixture, localized wall cleaning by Electron Cyclotron (EC) resonant plasma, and the development of machine learning-based disruption predictions, will be discussed in this paper.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"95 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140723288","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Iterative addition of parallel non-local effects to full wave ICRF finite element models in axisymmetric tokamak plasmas","authors":"Björn Zaar, Thomas J Johnson, Roberto Bilato, Pablo Antonio Vallejos Olivares","doi":"10.1088/1741-4326/ad3c51","DOIUrl":"https://doi.org/10.1088/1741-4326/ad3c51","url":null,"abstract":"\u0000 The current response of a hot magnetized plasma to a radio-frequency wave is non-local, turning the electromagnetic wave equation into an integro-differential equation. Non-local physics gives rise to wave physics and absorption processes not observed in local media. Furthermore, non-local physics alters wave propagation and absorption properties of the plasma. In this work, an iterative method that accounts. for parallel non-local effects in 2D axisymmetric tokamak plasmas is developed, implemented, and verified. The iterative method is based on the finite element method and Fourier decomposition, with the advantage that this numerical scheme can describe non-local effects while using a high-fidelity antenna and wall representation, as well as limiting memory usage. The proposed method is implemented in the existing full wave solver FEMIC and applied to a minority heating scenario in ITER to quantify how parallel non-local physics affect wave propagation and dissipation in the ion cyclotron range of frequencies (ICRF). The effects are then compared to a reduced local plane wave model, both verifying the physics implemented in the model, as well as estimating how well a local plane wave approximation performs in scenarios with high single pass damping. Finally, the new version of FEMIC is benchmarked against the ICRF code TORIC.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"106 8","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140724729","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Broadening of electron cyclotron power deposition and driven current profiles caused by dissipative diffractive propagation","authors":"K. Yanagihara, S. Kubo","doi":"10.1088/1741-4326/ad3c53","DOIUrl":"https://doi.org/10.1088/1741-4326/ad3c53","url":null,"abstract":"\u0000 Improvements of the Electron Cyclotron Resonance Heating (ECRH) and Current Drive (ECCD) predictions are important issues to design and control the high-performance fusion plasmas in future devices, where those should play a more important role as an actuator than in devices to date. The newly developed EC-prediction package based on the quasioptical ray tracing code PARADE revealed in JT-60SA that (i) radial profiles of both EC power deposition and driven current are broadened and (ii) the net driven current is increased by few kA/MW, in comparison with conventional predictions due to the dissipative diffractive propagation (DDP). The mechanism of DDP is as follows; EC wave beam obliquely passing through the resonant surface is dissipated non- uniformly on its beam cross section, so that the beam trajectory shifts gradually and thus the resonant position also shifts, resulting in the broadened power deposition profile. This novel ECCD and ECRH prediction package based on PARADE is applicable not only to JT-60SA but other existing devices and even, future devices.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"58 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140723867","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"COREDIV simulations of D and D-T high current-high power Baseline pulses in JET-ITER Like Wall","authors":"G. Telesca, Anthony Robert Field, I. Ivanova-Stanik, S. Brezinsek, A. Chomiczewska, D. Frigione, L. Garzotti, E. Kowalska-Strzeciwilk, Peter Lomas, J. Mailloux, Gianluca Pucella, F. Rimini, D. van Eester, Roman Zagórski","doi":"10.1088/1741-4326/ad3bcd","DOIUrl":"https://doi.org/10.1088/1741-4326/ad3bcd","url":null,"abstract":"\u0000 The two best performing pulses of the so called ITER-Baseline scenario (Ip=3.5 MA and Pin≈ 35 MW) of JET ILW, one in deuterium (D) the other in deuterium-tritium (D-T) plasma are examined and compared in this study. Generally, the D-T Baseline pulses exhibit an electron density level higher than the D pulses and the plasma energy is higher than in the comparable D pulses by up to 20%, reaching about 12 MJ in the pulse studied here. In contrast with the D pulses, the D-T pulses are often characterized by the increase in time of the radiated power in the mantle region, which may lead to the loss of the ELM activity when the threshold H-L transition power is approached and to the subsequent plasma disruption due to excessive radiation. In this study we try to identify the physical mechanisms responsible for this behaviour using the available experimental data (principally the total radiated power from the bolometry) and the results of the steady state fluid COREDIV model (1-D in the core, 2-D in the SOL), self-consistent with respect to core-SOL and to main plasma-impurities. The electron density and temperature profiles are numerically reconstructed as well as the radiated power density profiles, indicating no major difference in impurity transport in D and D T. In fact, the impurity transport coefficients used in COREDIV to match the experimental radiated power profiles are similar in the two pulses. The computed tungsten sources and densities are lower in the D-T pulse and the divertor impurity retention capability is a little better in the D-T pulse, indicating a stronger collisional drag force in the SOL. The higher electron density and the broadening of its profile are the main cause of the observed increase of the radiated power in the D-T pulse.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"28 16","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140732154","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Transport-driven toroidal rotation with general viscosity profile","authors":"T. Stoltzfus-Dueck, R. W. Brzozowski","doi":"10.1088/1741-4326/ad3bcc","DOIUrl":"https://doi.org/10.1088/1741-4326/ad3bcc","url":null,"abstract":"\u0000 Using the assumption of a weak normalized turbulent viscosity, usually valid in practice, the modulated-transport model [Stoltzfus-Dueck Phys. Plasmas 19: 055908 (2012)] is generalized to allow the turbulent transport coefficient to vary in an arbitrary way on radial and poloidal position. The new approach clarifies the physical interpretation of the earlier results and significantly simplifies the calculation, via a boundary-layer asymptotic method. Rigorous detailed appendices verify the result of the simple boundary-layer calculation, also demonstrating that it achieves the claimed order of accuracy and providing a concrete prediction for the strong plasma flows in the immediate vicinity of the last closed flux surface. The new formulas are used to predict plasma rotation at the core-edge boundary, in cases with and without externally applied torque. Dimensional formulas and extensive discussion are provided, to support experimental application of the new model.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"31 9","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140728082","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Overview of the KSTAR experiments toward fusion reactor","authors":"W. Ko, S. Yoon, Woong-Chae Kim, Jong-Gu Kwak, Kaprai Park, Y. Nam, Sonjong Wang, J. Chung, Byoung-Ho Park, Gunyoung Park, H.H. Lee, Hyunsun Han, M. Choi, Yong-Su Na, Yongkyoon In, Chan-Young Lee, Minwoo Kim, Gunsu S Yun, Y. Ghim, Wonho Choe, Jaemin Kwon, Jungpyo Lee, Woochang Lee, Y. Jeon, Kimin Kim, Jongha Lee, G. Shin, Jayhyun Kim, Jaehyun Lee, S. Hahn, Jeongwon Lee, Hyun-Seok Kim, J. Bak, S. G. Lee, Youngho Lee, J. Jeong, Minho Woo, Junghee Kim, J. Juhn, Jinseok Ko, C. Sung, Haewon Shin, J. M. Park, SangKyeun Kim, Jong-Kyu Park, N. Logan, S. Yang, E. Kolemen, Q. Hu, R. Shousha, J. Barr, C. Paz-Soldan, Young-Seok Park, S. Sabbagh, Katsumi Ida, Sun-Ho Kim, Alberto Loarte, E. Gilson, D. Eldon, Tomohide Nakano, T. Tala, Kstar Team","doi":"10.1088/1741-4326/ad3b1d","DOIUrl":"https://doi.org/10.1088/1741-4326/ad3b1d","url":null,"abstract":"\u0000 The KSTAR has been focused on exploring the key physics and engineering issues for future fusion reactors by demonstrating the long pulse operation of high beta steady-state discharge. Advanced scenarios are being developed with the goal for steady-state operation, and significant progress has been made in high ℓi, hybrid and high beta scenarios with βN of 3. In the new operation scenario called FIRE, fast ions play an essential role in confinement enhancement. GK simulations show a significant reduction of the thermal energy flux when the thermal ion fraction decreases and the main ion density gradient is reversed by the fast ions in FIRE mode. Optimization of 3D magnetic field techniques, including adaptive control and real-time machine learning (ML) control algorithm, enabled long-pulse operation and high-performance ELM-suppressed discharge. Symmetric multiple shattered pellet injections and real-time DECAF are being performed to mitigate and avoid the disruptions associated with high-performance, long-pulse ITER-like scenarios. Finally, the near-term research plan will be addressed with the actively cooled tungsten divertor, a major upgrade of the NBI and helicon current drive heating, and transition to a full metallic wall.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"4 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140735764","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Interpretative 3D MHD modelling of deuterium SPI into a JET H-mode plasma","authors":"Mengdi Kong, E. Nardon, Matthias Hoelzl, Daniele Bonfiglio, D. Hu, Sang Jun Lee, Roman Samulyak, U. Sheikh, S. Silburn, J. Artola, A. Boboc, G. Bodner, Pedro Carvalho, Ephrem Delabie, Josep Maria Fontdecaba Climent, Sergei Gerasimov, T. Hender, Stefan Jachmich, Domagoj Kos, K. Lawson, Stanislas Pamela, C. Sommariva, Ž. Štancar, B. Stein-Lubrano, Hongjuan Sun, Ryan Sweeney, G. Szepesi","doi":"10.1088/1741-4326/ad3b1c","DOIUrl":"https://doi.org/10.1088/1741-4326/ad3b1c","url":null,"abstract":"\u0000 The pre-thermal quench (pre-TQ) dynamics of a pure deuterium (D2) shattered pellet injection (SPI) into a 3MA/7MJ JET H-mode plasma is studied via 3D non-linear MHD modelling with the JOREK code. The interpretative modelling captures the overall evolution of the measured density and radiated power. The simulations also identify the importance of the drifts of ablation plasmoids towards the tokamak low field side (LFS) and the impurities in the background plasma in fragment penetration, assimilation, radiative cooling and MHD activity in D2 SPI experiments. It is found that plasmoid drifts lead to an about 70% reduction of the central line-integrated density (compared to a simulation without drifts) in the JET D2 SPI discharge considered. Impurities that pre-exist before the SPI as well as those from possible impurity influxes related to the SPI are shown to dominate the radiation in the considered discharge. With inputs from JOREK simulations, modelling with the Lagrangian particle-based pellet code PELOTON reproduces the deviation of the SPI fragments in the direction of the major radius as observed by the fast camera. This confirms the role of rocket effects and plasmoid drifts in the considered discharge and reinforces the validity of the JOREK modelling. The limited core density rise due to plasmoid drifts and the strong radiative cooling and MHD activity with impurities (depending on their species and concentration) could limit the effectiveness of LFS D2 SPI in runaway electron avoidance and are worth considering in the design of the ITER disruption mitigation system.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"12 6","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140737285","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Comparison of reduced model predictions for divertor detachment onset and reattachment timescales in ASDEX Upgrade and JET experiments","authors":"S. Henderson, Matthias Bernert, D. Brida, M. Cavedon, Pierre David, Ralph Dux, O. Février, Philippe Jacquet, A. E. Järvinen, Arne Kallenbach, J. Karhunen, K. Kirov, M. Komm, Morten Lennholm, B. Lomanowski, Chris Lowry, R. McDermott, Andy Meigs, Holger Reimerdes, Hongjuan Sun, Beth Thomas","doi":"10.1088/1741-4326/ad3970","DOIUrl":"https://doi.org/10.1088/1741-4326/ad3970","url":null,"abstract":"\u0000 Building on prior analysis of ASDEX Upgrade (AUG) experiments (Henderson et al. Nucl. Fusion 63 086024 2023), this study compares simple analytical formula predictions for divertor detachment onset and reattachment timescales in JET experiments. Detachment onset primarily scales with divertor neutral pressure, impurity concentration, power directed to the targets, machine size, and integral perpendicular power decay length. JET experiments, focusing on seeding mixtures of Ne and Ar, align with the detachment onset predictions. Radiation efficiencies among the impurities show good agreement with the model predictions, contrasting with AUG observations which suggested higher efficiency for Ar and lower efficiency for Ne. The time taken to re-ionise the neutral volume in front of the outer target in fully detached divertor conditions was measured following both abrupt increases in injected neutral beam power and, separately, cutting of the impurity gas flow. Reionisation of the neutrals occurs within approximately 1 second on JET, which aligns with the simple model prediction derived from AUG data. While the ASDEX Upgrade results are not new, their comparison with the JET results enhances understanding, reinforcing confidence in using simple models to predict future reactor scenarios.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"22 20","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-04-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140753680","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Plasma profile reconstruction supported by kineticmodeling","authors":"Michael George Bergmann, Rainer Fischer, Clemente Angioni, K. Höfler, Pedro Molina Cabrera, T. Görler, T. Luda, Roberto Bilato, G. Tardini, F. Jenko","doi":"10.1088/1741-4326/ad3138","DOIUrl":"https://doi.org/10.1088/1741-4326/ad3138","url":null,"abstract":"\u0000 Combining the analysis of multiple diagnostics and well-chosen prior information in the framework of Bayesian probability theory, the Integrated Data Analysis code (IDA) can provide density and temperature radial profiles of fusion plasmas. These IDA-fitted measurements are then used for further analysis, such as discharge simulations and other experimental data analysis. Since IDA considers uncertain measurement data from a heterogeneous set of diagnostics, the fitted profiles and their gradients may be in contradiction to well-established expectations from transport theory. Using the modeling suite ASTRA coupled with the quasi-linear transport solver TGLF, we have created a loop in which simulated profiles and their uncertainties are fed back into IDA as an additional prior, thus providing constraints about the physically reasonable parameter space. We apply this physics-motivated prior to several different plasma scenarios and find improved heat flux match, while still matching the experimental data. This work feeds into a broader effort to make IDA more robust against measurement uncertainties or lack of measurements by combining multiple transport solvers with different levels of complexity and computing costs in a multi-fidelity approach.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"8 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-03-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140077490","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Plasma surrogate modelling using Fourier Neural Operators","authors":"Vignesh Gopakumar, S. Pamela, L. Zanisi, Zong-Yi Li, Ander Gray, Daniel Brennand, Nitesh Bhatia, Gregory Stathopoulos, Matt Kusner, Marc Deisenroth, A. Anandkumar","doi":"10.1088/1741-4326/ad313a","DOIUrl":"https://doi.org/10.1088/1741-4326/ad313a","url":null,"abstract":"\u0000 Predicting plasma evolution within a Tokamak reactor is crucial to realizing the goal of sustainable fusion. Capabilities in forecasting the spatio-temporal evolution of plasma rapidly and accurately allow us to quickly iterate over design and control strategies on current Tokamak devices and future reactors. Modelling plasma evolution using numerical solvers is often expensive, consuming many hours on supercomputers, and hence, we need alternative inexpensive surrogate models. We demonstrate accurate predictions of plasma evolution both in simulation and experimental domains using deep learning-based surrogate modelling tools, viz., Fourier Neural Operators (FNO). We show that FNO has a speedup of six orders of magnitude over traditional solvers in predicting the plasma dynamics simulated from magnetohydrodynamic models, while maintaining a high accuracy (MSE ≈ 10−5). Our modified version of the FNO is capable of solving multi-variable Partial Differential Equations (PDE), and can capture the dependence among the different variables in a single model. FNOs can also predict plasma evolution on real-world experimental data observed by the cameras positioned within the MAST Tokamak, i.e., cameras looking across the central solenoid and the divertor in the Tokamak. We show that FNOs are able to accurately forecast the evolution of plasma and have the potential to be deployed for real-time monitoring. We also illustrate their capability in forecasting the plasma shape, the locations of interactions of the plasma with the central solenoid and the divertor for the full duration of the plasma shot within MAST. The FNO offers a viable alternative for surrogate modelling as it is quick to train and infer, and requires fewer data points, while being able to do zero-shot super-resolution and getting high-fidelity solutions.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"38 24","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-03-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140077133","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}