Recent Publications

Sep 8

Nuclear Fusion

A composite impurity-pressure index for assessing startup readiness during plasma recovery on EAST

Shuqi Yang, Yaowei Yu, Tao Zhang, Xiang Zhu, G Z Zuo, Xiang Gao

Reliable restart after vessel venting is controlled by the burn-through power balance: the plasma must ionize the residual neutrals, dissociate molecules and raise the electron temperature before ionization, charge-exchange and impurity-radiation losses exhaust the available ohmic or auxiliary power. In practice, however, operators usually do not know whether the wall has recovered until a shot has already been attempted. Six EAST plasma-recovery campaigns from 2023 to 2025 are analysed, and a pre-shot impurity-pressure index is introduced to combine the neutral pressure measured 2–3 s before breakdown with a weighted residual-gas-analyser proxy for nitrogen- and oxygen-bearing species. In this dataset, the index organises discharge duration, stable-shot probability and the loop voltage during the first 50–200 ms more clearly than either pressure or composition alone. Under the standard EAST startup condition used here, stable discharges become much more likely when the index falls to around 1 × 10-7 Pa. In the second 2025 campaign, the shot-by-shot evolution also shows threshold-like burn-through behaviour: the maximum line-averaged electron density in 0–0.2 s stays low at large index values, overshoots in a transition interval, and then settles to a more stable level as the wall recovers. Across campaigns, post-recovery values cluster much more tightly than the recovery paths themselves, indicating that the index characterizes the startup-ready wall state rather than a particular conditioning route. The metric therefore provides a practical pre-shot indicator of whether EAST has recovered sufficiently for reproducible stable startup.

Sep 4

Nuclear Fusion

Helium‑3 minority heating with ion cyclotron range of frequencies (ICRF) in the experimental advanced superconducting tokamak

Yongxin Zhu, Wei Zhang, Yevgen Kazakov, Jinhua Wu, Paola Mantica, Gabriele Cassella, Tao Jin, X. J. Zhang, Lunan Liu, Hua Yang, et al.

During the 2025 campaign, helium-3 ( 3 He) minority heating with waves in the ion cyclotron range of frequencies (ICRF) was investigated for the first time on the Experimental Advanced Superconducting Tokamak (EAST). With the lowest available ICRF frequency of f IC = 27 MHz, experiments were conducted at a high toroidal magnetic field of B t = 2.8 T and plasma current I p = 450 kA. To optimize 3 He minority heating, the variation of 3 He concentration was systematically explored. Real-time feedback control of the 3 He concentration was successfully implemented through spectroscopic measurement and closed-loop regulation of the 3 He gas injection, demonstrating the feasibility of the control system functions. The ICRF heating efficiency reached a maximum at a minority concentration of ∼8-9%, with the core electron temperature increasing from approximately 5.0 to 7.0 keV and the ion temperature from approximately 1.3 to 1.9 keV under 2.9 MW of ICRF power. These results are in good agreement with simulations from the two-dimensional full-wave code TORIC. Experiments further indicate that higher plasma density enhances 3He heating efficiency. We also briefly discuss the strategy for future 3 He ICRF experiments on EAST.

Sep 2

Nuclear Fusion

Dimensionless analysis of H-mode plasmas for energy confinement and transport on EAST tokamak

Can Su, Shouxin Wang, Haiqing Liu, Xiao Lan Zou, Shiying Su, Zhuoyang Chen, Zheng Sun, Chen Cheng, Zichao Lin, Guangle Lin, et al.

Nuclear FusionSep 2, 2026Plasma & Confinement

This work presents an investigation of dimensionless parameter scaling laws for H-mode energy confinement and transport on EAST tokamak, through dedicated experiments designed to isolate the individual effects of normalized plasma pressure ( β ) and collisionality ( ν * ). The β scaling experiment revealed a weak dependence of energy confinement time on β, resulting in a scaling exponent of α β ≈ 0.24±0.20. This weak positive dependence, consistent with experiment observations and linear simulations, reflects an electrostatic turbulence dominated confinement regime in EAST H-mode plasmas. In contrast, a strong, negative dependence of confinement time on ν * was obtained, following the scaling B τ E ∝ ν * -0.71±0.32, indicating confinement improvement with decreasing ν * . Local transport analysis indicates that this strong ν* dependence is primarily associated with electron heat transport, while ion heat transport exhibits a comparatively weak sensitivity. While the linear instability spectrum is dominated by ion temperature gradient (ITG) modes across the explored parameter range, ν * strongly regulates turbulence characteristics relevant to electron heat transport, leading to a pronounced ν* dependence of global confinement. These distinct behaviors of electron and ion heat transport are associated with different physical mechanisms governing the confinement scaling with dimensionless parameters.The present results suggest that the confinement scaling exponents observed on EAST are closely tied to the turbulence regimes accessed in the dedicated β and ν* scans, providing physical insight into the differences with respect to global multi-machine scaling trends.

Sep 1

Nuclear Fusion

Experimental observation of neoclassical tearing mode stabilization by ICRF drive in EAST

Hua Yang, Wei Zhang, Lunan Liu, Pengjun Sun, tao JIN, Hui-Hui Wang, Liqing Xu, Zhengshuyan Wang, Tonghui Shi, Hailin Zhao, et al.

Neoclassical tearing modes (NTMs) in high-beta plasmas can degrade confinement and trigger disruptions. Experiments were conducted on EAST to investigate the effects of ion cyclotron range of frequency (ICRF) heating on NTMs through controlled variation of the power deposition location and fast-ion distribution. Using hydrogen minority heating, on-axis and off-axis ICRF heating scenarios were achieved by varying the toroidal magnetic field, together with additional ICRF power modulation. The results show that on-axis ICRF heating effectively suppresses the m/n = 3/2 tearing mode, while off-axis heating tends to enhance the m/n = 4/3 mode. On-axis heating also improves plasma confinement and increases the neutron yield. TROIC-TRANSP simulations confirm the distinct power deposition locations, while ASCOT calculations indicate that the fast-ion energy reaches up to 800 keV during on-axis heating, which is substantially higher than that in the off-axis cases. A modified Rutherford equation incorporating fast-ion effects suggests that the fast-ion-driven uncompensated cross-field current term is responsible for the observed NTM behaviors. These results demonstrate that controlling the ICRF resonance position is a feasible approach for NTM suppression and improved plasma performance.

Aug 28

Nuclear Fusion

Simulation study of tungsten erosion and impurity transport under the assumption of a full-tungsten wall in EAST plasmas

Wu YiHan, Xuele Zhao, Chaofeng Sang, Yilin Wang, Chen Zhang, Qingrui Zhou, Dezhen Wang, Rui Ding, Baoguo Wang, Qingquan Yang, et al.

Future fusion reactors are expected to employ full-tungsten plasma-facing components, and the generation and core accumulation of tungsten impurities under full-tungsten wall environment is one of the key issues that limit the stable operation of tokamak devices. In this work, the upgraded impurity transport code IMPEDGE is coupled with the extended-grid version of SOLPS-ITER to investigate the erosion and transport of tungsten impurity in full-tungsten wall environment. The background plasma is based on experimental data from EAST discharge #140718, with all plasma-facing components assumed to be tungsten. The simulations show that, under full-tungsten wall assumption, both the tungsten impurity erosion and its core concentration remain at relatively high levels even in the detached regime, with dominant contributions originating from the far scrape-off layer (far-SOL) of the lower divertor and the upper divertor region. The main reason is that, although the electron temperature at the near scrape-off layer (near-SOL) of the lower divertor decreases significantly during detachment, that in the far-SOL region remains difficult to further reduce (~10 eV), resulting in substantial tungsten erosion. The total impurity penetration probability (defined as the probability for emitted particles to enter the plasma core) also remains at a relatively high level, mainly because the lower plasma density in the far-SOL weakens the impurity screening effect. In the downstream region, the reduced ion density decreases the friction force acting on impurities, allowing them to more easily escape from the region and migrate upstream. In the upstream region, the lower electron density increases the ionization mean free path, causing impurities to be ionized closer to the last closed flux surface and thereby enhancing impurity penetration. These results indicate that impurity screening in the near-SOL divertor region can be significantly enhanced by impurity-seeded detachment. However, erosion and penetration from the far-SOL region still dominate the core impurity accumulation, suggesting that more effective impurity control strategies for the far-SOL region are required in future studies.

Aug 20

Nuclear Fusion

Progress of understanding the effect of helium concentration on ion-electron collision and energy confinement on EAST

Qian Wang, Bin Zhang, Xianzu Gong, Jinping Qian, Xiaoming Zhong, Kedong Li, Wenbin Liu, Tianqi Jia, YuTong Guo, Wei Wang, et al.

Helium plasma experiments conducted on different tokamaks all demonstrate that the energy confinement are lower than those of deuterium plasmas under similar operation conditions. However, the origin of the difference in confinement between helium and hydrogen istopes remains unclear. To understand the influence of helium concentration, which leads to the variation of ion mass and charge number, on energy confinement, new helium experiments were conducted in the EAST tokamak with dominant electron heating and a tungsten divertor in 2025. A notable dependence on both ion mass and charge number is observed in the effective diffusion coefficient, as predicted by the gyro-bohm scaling χgB ∝ρi . The higher energy confinement time is observed with a lower ion mass. Conversely, when both the ion mass and charge number are increased, the energy confinement time is found to be similar. Power balance and transport analyses indicate that the ion-electron collision, significantly influenced by the variation of ion mass and charge number, appears to play a dominant role in regulating ion-scale turbulence in helium H-mode discharges. Furthermore, linear electromagnetic gyrokinetic simulation reveals that the Electron Temperature Gradient (ETG) turbulence was suppressed through the enhancement of ion-electron energy exchange in L-mode discharges. Consequently, it is crucial to take into account the role of electron-ion collision/energy exchange to understand the influence of ion mass and charge number on energy confinement. These results contribute to a better understanding of the transport characteristics in multi-ion-component plasma.

Aug 18

Nuclear Fusion

Characteristics of core beta-induced Alfvén eigenmodes with shear flow in EAST NBI heating plasmas

Lizhe Guo, Jian Bao, Ming Xu, Hailin Zhao, Yingying Li, Chao Dong, Jintao Cao, Zhiyong Qiu, Wenlu Zhang, Zhihong Lin, et al.

The basic features and relationship with zonal flows of multiple branches of beta-induced Alfv'en eigenmodes (BAEs) are investigated in the EAST tokamak. Those branches of BAEs, excited by tangentially injected NBI, are located in the central region ($0.2 \leq \rho \leq 0.4$), with frequencies in the range of 50 $\leq f \leq$ 70~kHz and low toroidal mode numbers $1 \leq n \leq 5$. The excitation of BAEs is clearly characterized by three typical features: an increase in the $\omega_{EXB}$ shear locally, accompanied by simultaneous rises in both central rotation velocity and electron temperature. Radial profiles of the mode phase angle from electron cyclotron emission (ECE) diagnostics vary significantly with $n$. Global gyrokinetic simulations of core BAEs are performed in both linear and nonlinear regimes. In the linear regime, the unstable BAE branches are consistent with experiment on toroidal mode number, real frequency and the mode structure phase angle. The radial variation of BAE phase angle is primarily caused by bulk plasma kinetic effects rather than the energetic particle (EP) non-perturbative drive. In the nonlinear regime, single-$n$ BAE without zonal fields saturates at a large amplitude that triggers the non-adiabatic frequency chirping on a fast timescale of sub-millisecond, while the self-organized zonal flow beat-driven by BAE greatly reduces BAE saturation amplitude below the chirping threshold, which is in consistency with experimental observation. Moreover, it is confirmed that the criterion of zonal flow regulation on dissipative-type instability (such as AEs) becomes $\omega_{E\times B} > \omega_r$ rather than traditional $\omega_{E\times B} > \gamma_L$ for reactive-type instability. In general, the self-organized zonal flow can improve plasma confinement through regulating both BAEs and drift-wave turbulence.

Aug 17

Plasma Physics and Controlled Fusion

DKEKAN: A single-parameterized KAN surrogate for Drift Kinetic Equation Toward Fast Neoclassical Toroidal Viscosity Torque Modeling in Tokamaks

Jinpeng Huang, Xingting Yan, Mingyu Zhang, Nana Bao, Zixuan Song, Yuetao Meng, Weiyong Zhou, Youwen Sun

Plasma Physics and Controlled FusionAug 17, 2026Plasma & ConfinementAI, Modeling & Simulation

The neoclassical toroidal viscosity (NTV) torque is a critical driver of toroidal rotation in tokamaks, profoundly influencing plasma stability and performance. Consequently, incorporating NTV effects is essential for modern integrated modeling frameworks that aim to self-consistently unify multiple physical processes. However, the high computational cost of NTV modeling precludes its self-consistent integration within such frameworks. This bottleneck arises because NTV calculation requires solving its governing equation--the drift kinetic equation (DKE)--in high-dimensional phase space. To address this issue, this study develops DKEKAN, a single-parameterized Kolmogorov-Arnold Network (SKAN) surrogate for solving DKE, to realize fast NTV modeling in tokamaks. The research process consists of the following steps: Firstly, a large dataset mapping DKE equation parameters to solutions is generated based on first-principle simulations under plasma parameters of the Experimental Advanced Superconducting Tokamak (EAST); Secondly, a surrogate model for solving DKE is developed based on the SKAN framework, which also incorporates a modular expert network design; Finally, the DKEKAN surrogate model is integrated with the NTV modeling framework to realize fast NTV calculation. With its physics-grouped expert layer and SKAN backbone, DKEKAN outperforms the tested MLP, KAN, and neural-operator baselines in overall prediction accuracy, while reducing the standalone DKE-solving time from 35.85s to 3.74s, corresponding to a speedup of approximately 9.6x, and reducing the total coupled NTVTOK runtime from 38.24s to 5.58s, corresponding to an overall speedup of approximately 6.9x. This work effectively overcomes the computational bottleneck in NTV simulations, thus supporting further integrated modeling that incorporates NTV effects.

Aug 14

Nuclear Fusion

Progress of LHCD experiment at 4.6 GHz towards long-pulse and high-power operation on EAST

Miaohui Li, Weiwei Zhang, Junlin Chen, Chenbin Wu, Bojiang Ding, Mao Wang, Liang Liu, Lianmin Zhao, Wendong Ma, Yong Yang, et al.

Recent achievements of lower hybrid current drive (LHCD) experiment at 4.6 GHz towards long-pulse and high-power operation on EAST tokamak are reported. The duration of long-pulse plasmas has been extended to 1056 s with 1.1 MW LH power in I-mode and 1066 s with 0.92 MW in H-mode. The operational domains in plasma current and line-averaged density for fully non-inductive discharges with LH alone and with the combined LH and electron cyclotron (EC) waves are presented. The dependence of LHCD efficiency on plasma density in both L- and H-mode discharges characterized by residual loop voltage Vloop = 0 is quantified. It is found that the LHCD efficiency is improved significantly by EC heating due to the increase of electron temperature. The dominant issues in long-pulse and high-power operation are summarized and discussed, including the power coupling imbalance, the hot spot and arc events in front of the antenna, and the deteriorated plasma heating effect with high LH power. Finally, prospects with a new 4 MW LHCD system at 4.6 GHz which is under development are given.

Aug 11

Nuclear Fusion

Nonlinear dynamic evolution of energetic particle mode due to nonadiabatic wave-particle interaction

Pengjuan Su, Fulvio Zonca, Matteo Valerio Falessi, Jialei Wang, Yasushi Todo, Zhiyong Qiu

Nuclear FusionAug 11, 2026Plasma & Confinement

Adopting dedicated phase-space diagnostics, we analyze the nonlinear dynamic evolution of an energetic particle mode (EPM) due to nonlinear wave–particle interactions, including nonlinear frequency chirping and secular particle motion due to trapping and de-trapping. By tracking representative particle orbits, we show that the nonlinear evolution is dominated by continuous turnover of the distinct resonant populations via self-consistent trapping and de-trapping, rather than by adiabatic frequency sweeping of a fixed cohort. The resulting clump motion in phase space follows the instantaneous low-frequency resonance contour, leading to pronounced downward frequency chirping. The measured EPM frequency chirping rate scales linearly with the mode amplitude, as predicted by general theory.

Aug 10

Plasma Physics and Controlled Fusion

Observation of fast ion acceleration under EGAM in EAST pure ECRH plasma with tearing mode

Chaowei Mai, liqing xu, Shiyao Lin, Tianfu Zhou, Tonghui Shi, Kangning Geng, Yifei Jin, Yanmin Duan, Kaiyun Chen, Yan Chao, et al.

Plasma Physics and Controlled FusionAug 10, 2026Plasma & ConfinementHeating & Current Drive

In magnetically confined fusion plasmas heated only by Electron Cyclotron Resonance Heating (ECRH), ion temperature typically saturates in the 1–3 keV range. The EAST tokamak, equipped with an ITER-like tungsten divertor, has operated deuterium H-mode discharges with high-power pure ECRH. In a specific discharge, a continuous ion acceleration process is observed, with ion energy ranging from an off-axis supra-thermal component above 6 keV to an isolated Gaussian peak reaching 1.8 MeV. The acceleration occurs at the location of a large 2/1 magnetic island, and an EGAM-like electrostatic mode at ∼ 23 kHz is detected by microwave diagnostics. The MeV-range cutoff energy, the mode power, and the island width exhibit pairwise strong linear correlations (R2 > 0.9), and the three are spatially coincident. Transfer entropy analysis and a 0D collisional-radiative model suggest a mechanism from island to mode to ion acceleration, excluding a purely electric-field-driven process. These observations provide experimental evidence of MeV-range ion acceleration accompanied by an EGAM-like mode in a pure ECRH plasma without auxiliary ion heating, offering a new data point for understanding ion acceleration under ECRH operation in tungsten-wall devices, particularly with degraded boron wall coating

Aug 6

Plasma Physics and Controlled Fusion

Gas pressure dependence of stray particles in the dual-driver RF negative ion source of CRAFT NNBI

Yuwen Yang, Zhengkun Cao, Na Wang, Yongjian Xu, Wei Liu, Yuming Gu, Chundong Hu, Yahong Xie, Lizhen Liang, Jianglong Wei

Plasma Physics and Controlled FusionAug 6, 2026Heating & Current Drive

The negative-ion-based neutral beam injection (NNBI) system is a reliable plasma heating and current drive method for large-scale magnetic confinement fusion devices. In the negative ion source, the problem of stray particles is a serious and unavoidable issue. These stray particles are mainly produced through particle-gas interaction in the accelerator region and can be subsequently accelerated, leading to high-voltage breakdown and substantial thermal deposition on components. The gas pressure plays a key role in determining the frequency of particle-gas collisions and simultaneously influences plasma and beam parameters, which in turn affect the generation and transport of stray particles. A NNBI test facility has been constructed in the Comprehensive Research Facility for Fusion Technology (CRAFT) in China. To investigate the dependence of stray particles behaviour on gas pressure, three sets of experiments have been conducted on CRAFT NNBI test facility. As the gas pressure increased, the power load on the ground grid (GG) first decreased and then increased, exhibiting an unexpected minimum value in the pressure range of 0.40~0.45 Pa. A similar trend was observed for the vertical beam divergence, whereas the horizontal beam divergence increased monotonically with gas pressure. In contrast, the ejecting electron power, stripping loss, and backstreaming positive ion power were positively correlated with gas pressure. These results provide experimental insight into the complex role of gas pressure in stray particle generation and beam quality in NNBI systems.

Aug 1

Jul 30

Plasma Physics and Controlled Fusion

Effects of fusion-relevant gas atmospheres and pressures on hydrogen isotope characterization for fuel-retention diagnostics by LIBS

Hao Sun, Zhenhua Hu, Jian Wu, Ying Zhou, Xinyu Guo, Huace Wu, Fang Ding, Hai-Shan Zhou, Xingwen Li, Jiangang Li

Fuel retention in plasma-facing components (PFCs) affects the operational efficiency and safety of fusion devices. However, detection of retained fuel by Laser-Induced Breakdown Spectroscopy (LIBS) remains challenging because the Hα and Dα Balmer lines commonly used for hydrogen-isotope identification are separated by only about 0.18 nm, making their discrimination highly sensitive to fusion-relevant ambient conditions. In this study, LIBS was employed to systematically investigate Hα/Dα discrimination on real EAST-exposed graphite tiles under various simulated ambient conditions. Depth-resolved measurements showed that the second laser pulse generally provided a more favorable Hα/Dα emission ratio and improved fitting quality, with the noise-normalized RMS residual decreasing from 3.6 to 1.26 compared with the first pulse. Meanwhile, time-resolved plume analysis helped explain the role of ambient environments in governing spectral broadening and isotope discrimination. At 100 Pa, the initial plume-height expansion rates within 200 ns were 15.6, 14.2, and 8.0 km/s in He, air, and Ar, respectively, revealing pronounced gas-dependent differences in plasma expansion. Combined spectral and plume analyses showed that vacuum provided high spectral resolution but suffered from a relatively short plasma lifetime. Within the investigated ambient parameters, a helium atmosphere at a moderate pressure of 100 Pa offered the most favorable balance between plasma lifetime and spectral resolution. In contrast, higher pressures or denser gases tended to enhance Stark broadening, leading to more severe peak overlap and a narrower effective discrimination window. The effective discrimination window was evaluated using the resolution factor Rs, with Rs ≈ 1.5 taken as a reference for baseline separation. These findings provide practical guidance for LIBS-based fuel retention diagnostics under EAST-relevant conditions.

Jul 24

Jul 22

Nuclear Fusion

Numerical investigation of helium ash transport in CFETR steady state scenario

Zhihong Kuang, Wei Shen, Jiale Chen

In magnetic confinement fusion plasmas, the main product of deuterium-tritium fusion is energetic alpha particles, which transfer energy to the background plasma by collisions and become thermalized helium ash. Helium ash accumulation would cause fuel dilution and reduce plasma confinement performance and fusion gain. In this work, the transport of helium ash in CFETR is simulated by the advanced transport solver TGYRO, which invokes the NEO and TGLF codes to compute neoclassical and turbulent transport, respectively. By analyzing the neoclassical and turbulent transport of helium ash, it is found that ITG turbulence is dominant for helium ash transport in CFETR. In addition, with low helium ash fractions, the redistributed helium ash density is larger than the initial setting profile because the source rate exceeds the outward transport, while the helium ash density is smaller than the initial density with high helium ash fractions. Inside the ITB, ITG turbulence is suppressed, leading to a significant reduction in the outward transport of helium ash. The transport process of helium ash can have some influences on micro-instabilities. In particular, an increase in helium ash concentration may stabilize ITG turbulence. Redistributed energetic alpha particles due to Alfvén eigenmodes affect the helium ash transport by changing its source, but they do not significantly alter the helium ash distribution. Our work advances the understanding of the dominant physical mechanism governing helium ash transport in future fusion devices.

Jul 19

Plasma Physics and Controlled Fusion

Effect of the cusp magnets system on the hybrid RF ion source in NIFS by 2D fluid model

Na Wang, Katsuyoshi Tsumori, Masaki Osakabe, Haruhisa Nakano, Zhimin Liu, Yuanlai Xie

Plasma Physics and Controlled FusionJul 19, 2026Heating & Current DriveAI, Modeling & Simulation

A two-dimensional fluid model of the RF ion source in NIFS test stand was established using COMSOL Multiphysics to examine the influence of the cusp magnets on plasma transport and RF power coupling. Particular attention was paid to the magnetic field intensity of the cusp magnets on driver backplane and its impact on plasma behaviour in both the driver and the extraction region. Simulation results reveal that strong magnetic confinement from the upper cusp magnets suppresses cross-field plasma transport, leading to reduced electron density near the plasma grid and less efficient RF power deposition. To explore potential optimization, a modified configuration with two smaller magnets of half the original size was investigated. This adjustment significantly enhances plasma density, increasing the peak density in the driver by nearly a factor of two. However, the enhanced plasma density is accompanied by increased spatial gradients in the extraction region, indicating that plasma uniformity is not improved under the modified magnetic configuration. These results reveal a trade-off between plasma density enhancement and spatial uniformity, arising from the interplay between magnetic confinement and plasma transport. This study provides insight into the role of cusp magnetic fields in regulating plasma generation and spatial gradients, and highlights the importance of balancing plasma density and uniformity in the optimization of RF negative ion sources.

Jul 16

Nuclear Fusion

Investigation of Dynamic Radiation Belt Characteristics and Mechanisms in EAST Tokamak

Bingcheng Qi, Fang Ding, Qing Zhang, Tonghui Shi, Yue Yu, Jinju Yang, Jingsheng Yuan, Lin Yu, Lifeng Yang, Minrui Wang, et al.

Nuclear FusionJul 16, 2026Plasma & Confinement

A dynamic radiation belt—exhibiting characteristics of intense radiation, high density, and low electron temperature, akin to multifaceted asymmetric radiation from the edge (MARFE)—was observed and investigated in the Experimental Advanced Superconducting Tokamak (EAST). This belt forms in the divertor region with impurity injection and subsequently migrates towards the X-point and the high-field side (HFS) of the plasma boundary after the transition from H mode to L mode (H-L transition) or confinement degradation. The belt traverses the inner mid-plane, reaches the opposite divertor, and subsequently retreats back to its initial divertor location. This migration is accompanied by a concurrent evolution of poloidal asymmetry in key plasma parameters, including electron density, radiation profiles, neutral pressure, and wall heat load distribution. The migration of the radiation belt is closely related to the evolution of the edge neutral pressure. Reversing the toroidal magnetic field (BT) direction inverts both the initial position of the radiation belt and its trajectory. The reversal of neutral pressure asymmetry between upper and lower divertors following BT direction change demonstrates the role of B-direction-dependent drift effects. Furthermore, the migration of the radiation belt is consistently accompanied by localized fluctuations with frequencies up to 10 kHz in both plasma radiation and density signals. During belt migration, the magnetic oscillations transition from a broadband spectrum to a coherent narrowband emission, identified as an m/n=2/1 magnetohydrodynamic (MHD) instability mode. The frequency of the mode is positively correlated with the distance of the radiation belt from its initial position. Excessive increases in the magnetic oscillation frequency typically precede plasma disruptions, which may suggest a critical link between oscillation spectral characteristics and disruption onset mechanisms.

Jul 13

Nuclear Fusion

Investigation on the high-temperature creep and irradiated damage behaviours of plasma-facing components material fabricated by selective laser melting

Zhihong Liu, Zhiyong Wang, Jianguo Ma, Huapeng Wu, Nengtao Zhou, Wangqi Shi, Tao Zhu, Yudong Su, Jiefeng Wu

Oxide dispersion-strengthened (ODS) steel is a promising structural material in fusion reactors, nanoparticles in matrix pin grain boundaries, and capture point defects and they delay the performance degradation caused by creep and irradiation. In this paper, RAFM steel with Y 2 O 3 was formed by selective laser melting (SLM) and the microstructural evolution under creep and irradiation were closely studied. SLM-formed ODS-RAFM steel had a longer high-temperature creep life than RAFM steel at the same stress and temperature, the fined grains were closely related to recrystallisation and pinning of oxide. The ODS-RAFM steel exhibited great irradiation stability, the lath width slightly increased, and the hardening rate was smaller than RAFM steel. During the irradiation process, continuously precipitated new MX carbides and Y–Ta–O oxide occurred in ODS-RAFM steel, which resisted the growth of grains. The above research results explained the microstructural evolution of RAFM steel and the change of performance under high temperature and an irradiation environment of fusion reactors, which verified the significant role of Y 2 O 3 nanoparticles in maintaining high temperature stability and irradiation resistance, hence providing a strong theoretical basis for the ODS-RAFM steel of the future to be fully used as the blanket structural material of nuclear fusion reactors.

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