Nuclear Fusion最新文献

{"title":"Exploring the physics of a high-performance H-mode scenario with small ELMs at low collisionality in JET with Be/W wall","authors":"E. de la Luna, Jeronimo Garcia, M. Sertoli, Peter Lomas, Samuele Mazzi, Ž. Štancar, M. Dunne, Nobuyuki Aiba, S. Silburn, M. Faitsch, G. Szepesi, F. Auriemma, Itziar Balboa, L. Frassinetti, L. Garzotti, S. Menmuir, D. Réfy, F. Rimini, E. Solano, Carlo Sozzi, Milos Vecsei","doi":"10.1088/1741-4326/ad5fa0","DOIUrl":"https://doi.org/10.1088/1741-4326/ad5fa0","url":null,"abstract":"\u0000 A new H-mode regime at low density and low edge safety factor (q95=3.2, with Ip=3 MA) that combines high energy confinement, stationary conditions for density and radiation and small Edge Localized Modes (ELMs) have been found in JET with Be/W wall. Such a regime is achieved by operating without external gas puffing, leading to a decrease in the edge density and a substantial increase in rotation and ion temperature in both the pedestal and the core region. Transport modelling shows a reduction of the turbulence, which starts in the pedestal region and extends into the plasma core, and outward impurity convection, consistent with the improved energy confinement and the lack of W accumulation observed in those conditions. In addition, large type I ELMs, typically found in gas-fuelled plasmas, are replaced by smaller and more frequent ELMs, whose appearance is correlated with a substantial reduction of the pedestal density and its gradient. Pedestals in this operating regime are stable to peeling–ballooning modes, consistent with the lack of large ELMs. This is in contrast to results in unfuelled JET-C plasmas that typically operated at higher pedestal densities and developed low frequency, large type I ELMs, thus pointing to the low density as one of the critical parameters for accessing the small ELMs in JET. This small ELMs regime exhibits the same low pedestal collisionality (ν∗\u0000 e,ped ∼ 0.1) expected in ITER and operates at low q95, thus making it different from other small ELMs regimes typically obtained at higher q95 and higher pedestal collisionality. These features make this newly developed H-mode regime in JET with Be/W wall a valuable tool for exploring the underlying transport, the different mechanisms of turbulence stabilization, as well as the physics associated with the appearance of small ELMs in high-temperature plasmas at ITER relevant pedestal collisionality.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":" 47","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-07-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141673176","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":"Turbulence-reduced high-performance scenarios in Wendelstein 7-X","authors":"O. Ford, M. Beurskens, S. Bozhenkov, S. Lazerson, Lilla Vano, Arturo Alonso, J. Baldzuhn, C. Beidler, Christoph Biedermann, R. Burhenn, Golo Fuchert, D. Hartmann, Matthias Hirsch, A. Langenberg, Heinrich Laqua, P. McNeely, N. Pablant, E. Pasch, Felix Reimold, T. Romba, N. Rust, Ralf Schroeder, Evan Scott, Torsten Stange, Hakan M Smith, D. Gradic, R. C. Wolf, Daihong Zhang","doi":"10.1088/1741-4326/ad5e99","DOIUrl":"https://doi.org/10.1088/1741-4326/ad5e99","url":null,"abstract":"\u0000 In the Wendelstein 7-X (W7-X) stellarator, turbulence is the dominant transport mechanism in most discharges. This leads to a 'clamping' of ion temperature over a wide range of heating power, predominantly flat density profiles where hollow profiles driven by neoclassical thermo-diffusion would be expected and by rapid impurity transport in injection experiments. Significantly reduced turbulent transport is observed in the presence of strong core density gradients found transiently after core pellet injection and irregularly after boronisation or boron pellet injection. Density peaking is also achieved in a controlled manner in purely neutral beam heated discharges where particle transport analysis reveals an abrupt reduction in the main-ion particle flux leading to significant density profile peaking not explained by the NBI particle source alone. The plasmas exhibit a heat diffusivity of around chi=0.25±0.1 m^2 s^-1 at mid radius, a factor of around 4 lower than ECRH dominated discharges. Despite the improved confinement, the achieved ion temperature is limited by broader heat deposition and the lower power-per-particle given the higher density. This is overcome with limited reintroduction of ECRH power, where the low heat diffusivity diffusivity is maintained, the density rise supressed and ion temperatures above the clamping limit are achieved. The applicability of these plasmas for a high performance scenario on transport relevant time scales is assessed, including initial predictions for planned heating upgrades of W7-X, based on a range of assumptions about particle transport.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"94 8","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-07-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141683848","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":"Off-target gradient driven flows in 3D simulations of ADITYA-Upgrade tokamak scrape-off layer plasma transport","authors":"Arzoo Malwal, B. P. Sahoo, Devendra Sharma, Yuhe Feng","doi":"10.1088/1741-4326/ad5e95","DOIUrl":"https://doi.org/10.1088/1741-4326/ad5e95","url":null,"abstract":"\u0000 Coupled plasma-neutral transport simulations are performed of ADITYA-Upgrade tokamak scrape-off layer (SOL) plasma where flows in the core and SOL were measured to reverse sign with density variation. The simulations per- formed using EMC3-Eirene plasma-neutral code combination incorporate the toroidally continuous high-field-side belt-limiter placed in a moderate-circular tokamak equilibrium. Development of mutually counter-propagating toroidal plasma flows in top and bottom regions of both SOL and core is recovered for relatively high upstream density cases with high input power (300 kW and 3 m 2 s −1 ). The origin of the flows is traced to the poloidal density variation introduced by high recycling on the inboard localized belt limiter. The results are compared with the similar observations, for example, in Doppler shifted passive charge exchange line emission on the ADITYA-Upgrade (ADITYA-U) tokamak , highlighting the role played by residual stress in the total Reynold stress. The external stimuli, like a localized gas puff, are discussed as potential drivers of flow, by means of residual stress, based on the existing resonant model of the tokamak plasma rotation.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"78 2","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-07-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141682769","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":"Measurements of laser-plasma instabilities in double-cone ignition experiments relevant to the direct-drive conditions at Shenguang-II Upgrade laser facility","authors":"Xu Zhao, X. Yuan, Yufeng Dong, K. Glize, Yihang Zhang, Jun Zheng, C. Xing, Haochen Gu, Chenglong Zhang, Yu Dai, Ke Fang, Zhe Zhang, Yan Rui, Fuyuan Wu, Jie Zhang","doi":"10.1088/1741-4326/ad5e98","DOIUrl":"https://doi.org/10.1088/1741-4326/ad5e98","url":null,"abstract":"\u0000 Experiments have been performed to investigate laser-plasma instabilities (LPIs) relevant to the direct-drive inertial confinement fusion (ICF) conditions at the Shenguang-II Upgrade (SG-II UP) laser facility during the double-cone ignition (DCI) experimental campaigns, with the overlapped laser intensity ranging from 6×1014 W/cm2 to 1.8×1015 W/cm2. An overall LPI scenario has been built from the collection and investigation of angularly distributed scattered light. Across broad ranges of laser and plasma parameters, relevant to the direct-drive ICF conditions, the dominance of the stimulated Raman side scattering (SRSS) was confirmed, and its coexistence with the two-plasmon decay (TPD) was also observed. Significant SRSS scattered light was observed across an extremely wide range of emission angles, concentrated at large angles, and demonstrated to be robust throughout the parameter space. Time-resolved spectral measurements show distinctly different SRSS behaviors along different angles and a slightly higher threshold compared to the TPD. The overall SRSS energy loss was measured, indicating a scattered light energy fraction of up to 6%. These results are of crucial importance for the precise assessment of the LPIs in the DCI as well as other laser directly driven ICF schemes.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"112 4","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-07-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141681716","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":"Non-linear MHD investigations of high-confinement regimes without type-I ELMs in ASDEX Upgrade and JT-60SA","authors":"A. Cathey, M. Hölzl, Lorenz Meier, M. Dunne, G. Huijsmans, Luís Gil, G. Harrer, Nobuyuki Aiba, D. Cruz-Zabala, Karl Lackner, Stanislas Pamela, E. Viezzer, Elisabeth Wolfrum, Sibylle Günter","doi":"10.1088/1741-4326/ad5e97","DOIUrl":"https://doi.org/10.1088/1741-4326/ad5e97","url":null,"abstract":"\u0000 Large edge localised modes (ELMs) would cause an unacceptable reduction of material lifetime in future large tokamaks due to the significant amount of energy expelled from the magnetically confined region towards the plasma facing components. Thoroughly validated modelling of regimes devoid of large ELMs is crucial as it may then provide predictive insights prior to tokamak operation and design. This paper describes recent efforts pursued with the non-linear extended MHD code JOREK in the modelling of three scenarios without large ELMs: quiescent H-mode (QH-mode), quasi-continuous exhaust regime (QCE regime), and the enhanced D-alpha H-mode (EDA H-mode). For each of these regimes, the non-linear dynamics observed in the simulations are detailed and compared to experimental observations of the underlying instabilities of each regime (edge harmonic oscillation for QH-mode, small ELMs for QCE regime, and quasi-coherent mode for EDA H-mode). For QH-mode, the kink-peeling mode is found to govern the dynamics and a transition to a large ELM is obtained above the same density threshold as in the modelled experiment. For the QCE regime and EDA H-mode, resistive peeling-ballooning modes dominate and pedestal fluctuation amplitudes correspond well to experimental observations. The dominant mechanisms for the excitation and suppression of these instabilities is presented and their influence on simulation dynamics is shown. Finally, predictive simulations of edge instabilities at different values of plasma resistivity in a 4.60 MA scenario with low edge safety factor in JT-60SA are presented.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"82 3","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-07-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141683883","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":"Facilitated core-edge integration through divertor nitrogen seeding in the HL-2A tokamak","authors":"Na Wu, Jun Cheng, K. Yi, Rui Wang, Mingkun Han, Zhihui Huang, Weice Wang, Yu He, Longwen Yan, Hailong Du, Jinming Gao, Huicong Ma, Xiaoxue He, Zengchen Yang, J. Wen, Kai Zhang, Ting Wu, Wenping Guo, Xin Yu, Liang Liu, Yonggao Li, Lin Nie, Zhongbing Shi, Dezhen Wang, Wulyu Zhong","doi":"10.1088/1741-4326/ad5e96","DOIUrl":"https://doi.org/10.1088/1741-4326/ad5e96","url":null,"abstract":"\u0000 Divertor detachment with the sustainable high-performance plasmas has been achieved through divertor nitrogen seeding in the HL-2A tokamak. The closed divertor structure facilitates achieving high divertor neutral pressure due to its efficient particle containment effect as demonstrated by both experimental and SOLPS simulation results, which aids in achieving the divertor detachment. The radiative divertor is conducive to high-frequency small ELMs operation, characterized by the reduced pedestal ion temperature gradient ∇T_i and the enhanced electron density gradient ∇n_e. The presence of minority nitrogen at the edge plasma, which results from the divertor nitrogen seeding, contributes to the rise of ion temperature T_i in the confinement region by suppressing the turbulence through the impurity dilution effect and E×B shear. The increased ion temperature T_i and electron density n_e compensate the energy loss resulted from the increased edge radiation during detachment, which contributes to the confinement sustainment combined with reduced pedestal energy loss caused by small ELMs. This work advances our understanding on the fundamental physics governing the closed divertor detachment with sustainable high-performance plasmas through divertor nitrogen seeding.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"87 11","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-07-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141683545","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":"Origin of the up/down poloidal asymmetric dependence of ELM control in ITER-like RMP configuration in KSTAR","authors":"Inhwan Choi, Yueqiang Liu, Yongkyoon In","doi":"10.1088/1741-4326/ad5e93","DOIUrl":"https://doi.org/10.1088/1741-4326/ad5e93","url":null,"abstract":"\u0000 Recent edge-localized modes (ELM) control experiments via Resonant Magnetic Perturbation (RMP) in KSTAR have shown a strong up/down poloidal asymmetric coupling dependence. Specifically, in lower single null (LSN) plasmas at q95≳5, the lower two-row (middle/bottom) RMPs among ITER-like three-row (top/middle/bottom) in-vessel control coils (IVCC) in KSTAR were more effective in suppressing ELM-crashes than the upper two-row (top/middle) RMPs. In contrast, at q95~4, the upper two-row RMPs turned out to be more effective than the lower counterpart. Since the ITER baseline scenario is planned to operate at q95~3, the understanding of the origin of such up/down poloidal asymmetric coupling dependence, as well as the prediction about ITER-relevant conditions at a lower q95, would be quite important and potentially impactful to the RMP ELM control in ITER. A linear, resistive, single-fluid MHD code MARS-F has been utilized to address and model the up/down poloidal asymmetric RMP coupling dependence. Specifically, based on two contrasting exemplary discharges with up/down poloidal (i) asymmetric at q95~4 and (ii) symmetric behavior at q95~5, among tens of otherwise similar discharges, a systematic MARS-F modeling has been thoroughly conducted. As a result, the plasma response investigation suggests that the X-point displacement (ξX), rather than any other figures of merit, would be a directly relevant metric for the up/down poloidal asymmetric coupling in RMP-driven, ELM-crash suppression in KSTAR. Based on a sensitivity study of the edge safety factor in MARS-F modeling, the ξX variation follows the same quantitative trend as observed in experiments. However, no or little plasma pressure dependence has been found, though ξX increases with plasma pressure. At the ITER-relevant low q95~3 in a scaled KSTAR equilibrium, such modeling predicts the upper two-row RMPs would be more favorable in suppressing the ELM-crashes than the lower counterpart.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"72 4","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-07-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141684182","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":"Nonlinear simulation of peeling-ballooning instability of super H-mode in the HL-3 tokamak","authors":"Yiren Zhu, Wulyu Zhong, Xiao Lan Zou, Jiaxian Li, M. Xue, Zhengji Li, Lei Xue, Guoliang Xiao, Ruihai Tong, Y. Zou, Jiao Yin, Anshu Liang, Linzi Liu, B. Yuan, Min Xu","doi":"10.1088/1741-4326/ad5e94","DOIUrl":"https://doi.org/10.1088/1741-4326/ad5e94","url":null,"abstract":"\u0000 As the newly built tokamak in China, HL-3 is going to explore high performance operation scenario such as super H-mode. The energy confinement and core parameters in super H-mode can be much larger than that in normal H-mode. Based on the pedestal simulation code EPED, the operation space of super H-mode is obtained in HL-3. Magnetic shear decreases with increasing triangularity, and then the super H-mode can be achieved. The threshold of triangularity for accessing super H-mode in HL-3 is around 0.4. By using BOUT++, nonlinear simulation study of the pedestal instabilities in super H-mode equilibrium is executed for the first time. As expected, low n peeling mode which can cause much energy loss (17%) from the pedestal region is dominant in super H-mode. Such a big collapse at pedestal region will lead the transition of super H-mode to H-mode. It is crucial to expand the parameter space of the super H-mode or mitigate the ELM size for sustaining the super H-mode operation. E×B velocity shear is found to play an important role for controlling the ELMs in HL-3. On the one hand, small E×B velocity shear leads to large growth rate but small ELM size around peeling boundary. ELM size is closely related with both of growth rate of peeling-ballooning mode and duration time of linear phase. On the other hand, large E×B velocity shear can stabilize the instabilities near ballooning boundary, and then the parameter space of super H-mode will be enlarged.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"155 2","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-07-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141681796","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":"Contributions of the extended ELISE and BATMAN Upgrade test facilities to the roadmap towards ITER NBI","authors":"U. Fantz, Dirk Wünderlich, Christian Wimmer, M. Barnes, N. den Harder, B. Heinemann, Adrian Heiler, M. Lindqvist, F. Merk, Araceli Navarro, R. Nocentini, G. Orozco, R. Riedl, D. Yordanov, D. Zielke","doi":"10.1088/1741-4326/ad5dcd","DOIUrl":"https://doi.org/10.1088/1741-4326/ad5dcd","url":null,"abstract":"\u0000 ITER’s NBI systems are a first of its kind system with very challenging targets for the RF-driven ion source and the acceleration stage. In a step ladder approach, the ion source test facilities BATMAN Upgrade (BUG) and ELISE support the activities carried out at the Neutral Beam Test Facility (NBTF), Padua, which is equipped with the ion source facility SPIDER and with MITICA being equivalent to the ITER Heating Neutral Beam injector (HNB), capable of operating at the full power and pulse length of the ITER HNBs. The contributions of the prototype ion source at BUG (1/8 scale) and the size scaling experiment ELISE (1/2 size ITER source) to the roadmap are manifold: for hydrogen operation the ion source performance is demonstrated in several sequential 1000 s pulses, whereas long pulse deuterium operation is limited by the heat load of the co-extracted electrons on the extraction grid. Measures like special magnetic filter field configurations or biasing of surfaces and improved Cs management are identified. Both facilities have recently been extended to full steady state compatibility and very first insights of the ion source performance are already gained. A pulse length of 400 s, as required for the first deuterium campaigns at ITER, seems to be feasible soon, whereas the one hour pulse imposes the highest challenge to overcome. Investigations on beam divergence revealed a divergence at the upper limit of the acceptable value for the HNB. Measurements on the beam uniformity on the scale of beamlet groups and grid segments at ELISE demonstrated a uniformity of better than the required 90%. BUG and ELISE gave input to recent implementations at SPIDER; MITICA and ITER’s NBI. Still open points and challenges are addressed, for which a continuation of the step ladder approach is essential.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"23 8","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-07-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141685594","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":"Impact of various DIII-D diagnostics on the accuracy of neural network surrogates for kinetic EFIT reconstructions","authors":"Xuan Sun, Cihan Akcay, Torrin Bechtel, Scott Kruger, L. Lao, Yueqiang Liu, Sandeep Madireddy, Joseph McClenaghan","doi":"10.1088/1741-4326/ad5d7b","DOIUrl":"https://doi.org/10.1088/1741-4326/ad5d7b","url":null,"abstract":"\u0000 Kinetic equilibrium reconstructions make use of profile information such as particle density and temperature measurements in addition to magnetics data to compute a self-consistent equilibrium. They are used in a multitude of physics-based modeling. This work develops a multi-layer perceptron (MLP) neural network (NN) model as a surrogate for kinetic Equilibrium Fitting (EFITs) and trains on the 2019 DIIID discharge campaign database of kinetic equilibrium reconstructions. We investigate the impact of including various diagnostic data and machine actuator controls as input into the NN. When giving various categories of data as input into NN models that have been trained using those same categories of data, the predictions on multiple equilibrium reconstruction solutions (poloidal magnetic flux, global scalars, pressure profile, current profile) are highly accurate. When comparing different models with different diagnostics as input, the magnetics-only model outputs accurate kinetic profiles and the inclusion of additional data does not significantly impact the accuracy. When the NN is tasked with inferring only a single target such as the EFIT pressure profile or EFIT current profile, we see a large increase in the accuracy of the prediction of the kinetic profiles as more data is included. These results indicate that certain MLP NN configurations can be reasonably robust to different burning-plasma-relevant diagnostics depending on the accuracy requirements for equilibrium reconstruction tasks.","PeriodicalId":503481,"journal":{"name":"Nuclear Fusion","volume":"28 3","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141691093","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}