Dissipative nonlinear structures in tokamak plasmas by K. A. Razumova

“…A lot of different kinds of instabilities may be developed in high temperature plasma located in a strong toroidal magnetic field (tokamak plasma). Nonlinear effects in the instability development result in plasma self-organization. …”
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Boundary plasma studies for a spherical tokamak with lithium walls by A. Antony, L. Carbajal, T.D. Rognlien, M.V. Umansky, A. Froese, S. Howard, C. Ribeiro, R. Ivanov, C. Dunlea, C.P. McNally

“…The General Fusion magnetised target fusion technology uses coaxial helicity injection (CHI) start-up which forms a spherical tokamak in a cavity with liquid lithium walls that will subsequently be compressed to fusion conditions Laberge, J. …”
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The first application of flush probe arrays on HL-3 tokamak by Z.H. Huang, L.W. Yan, K.Y. Yi, Na Wu, W.J. Chen, W.C. Wang, Yu He, J. Chen, J. Cheng, W. Zhao, J.M. Gao, L. Nie, Z.B. Shi, X.Q. Ji, W.L. Zhong

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The impact of E × B shear on microtearing based transport in spherical tokamaks by B.S. Patel, M.R. Hardman, D. Kennedy, M. Giacomin, D. Dickinson, C.M. Roach

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Adaptive anomaly detection disruption prediction starting from first discharge on tokamak by X.K. Ai, W. Zheng, M. Zhang, Y.H. Ding, D.L. Chen, Z.Y. Chen, B.H. Guo, C.S. Shen, N.C. Wang, Z.J. Yang, Z.P. Chen, Y. Pan, B. Shen, B.J. Xiao, J-TEXT team

Subjects: “…tokamak…”
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Experimental study and gyrokinetic simulations of isotope effects on core heat transport in JET tokamak deuterium and tritium plasmas by D. Brioschi, P. Mantica, A. Mariani, N. Bonanomi, E. Delabie, J. Garcia, N. Hawkes, I. Jepu, D. Keeling, E. Lerche, E. Litherland-Smith, C.F. Maggi, S. Menmuir, G. Szepesi, D. Taylor, D. Van Eester, JET Contributors

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Research on ion cyclotron emission driven by deuterium–deuterium fusion-produced tritium ions on the Experimental Advanced Superconducting Tokamak by Huapeng Zhang, Lunan Liu, Wei Zhang, Xuan Sun, Xinjun Zhang, Zhengshuyan Wang, Zelin Xu, Jiadong Zhang, Weijian Qin, Liuxin Li, Yuhao Jiang, Sichun Qiu, Chengming Qin, Guanghui Zhu, Yongxin Zhu, Kai Zhang, Tao Jin, Zhiping Li

“…In the 2023 experiment campaign, we measured ion cyclotron emission (ICE) signals on the Experimental Advanced Superconducting Tokamak (EAST), edge ICE excited by tritium ions. …”
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Tearing stable stationary ITER baseline operation in DIII-D by L. Bardóczi, A. Dudkovskaia, N.C. Logan, N.J. Richner, A.C. Brown, J.D. Callen, R.J. La Haye, E.J. Strait

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Investigating the influence of divertor baffles on nitrogen-seeded detachment in TCV with SOLPS-ITER simulations and TCV experiments by G. Sun, H. Reimerdes, C. Theiler, B.P. Duval, M. Carpita, C. Colandrea, R. Ducker, O. Février, S. Gorno, L. Simons, E. Tonello, the EUROfusion Tokamak Exploitation Team, the TCV Team

Subjects: “…tokamak…”
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Tungsten erosion during L-mode discharges in the DIII-D SAS-VW divertor by G. Sinclair, T. Abrams, M.S. Parsons, S.H. Messer, J. Mateja, S.A. Zamperini, D.M. Thomas, J.D. Elder, R. Maurizio, T. Odstrcil, R.S. Wilcox, J.L. Herfindal, D.D. Truong, J.G. Watkins, A.G. McLean, D.L. Rudakov, J. Ren, D. Donovan

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The design and implementation of automated maintenance system for the first-wall based on dual-arm manipulator by Ke Wu, Jun Zhang, Yong Cheng, Qingxi Yang, Hongtao Pan, Tao Wang, Aiming Liu, Hao Han

Subjects: “…Tokamak device…”
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Transport and profile broadening in the private flux region of ASDEX upgrade and role for power exhaust by D. Brida, G. Grenfell, O. Grover, D. Silvagni, M. Faitsch, U. Stroth, the ASDEX Upgrade Team, the EUROfusion Tokamak Exploitation Team

“…Understanding the transport processes that determine the plasma profile widths in the scrape-off layer (SOL) and divertor region of tokamaks is crucial for successful power and particle exhaust management in future devices. …”
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Comparison of plasma start-up with high Z and low Z first wall in WEST by C. Guillemaut, K. Afonin, G. Bodner, J. Bucalossi, Y. Corre, P. Devynck, A. Diallo, M. Diez, N. Fedorczak, A. Gallo, B. Guillermin, V. Lapleigne, R. Lunsford, P. Maget, J. Morales, Ph. Moreau, the WEST Team, the EUROfusion Tokamak Exploitation Team

“…In this context, the present work focuses on the correlations between first wall impurity sources and total radiated power during plasma start-up in the tungsten (W) Environment in Steady-state Tokamak (WEST). The objective is to highlight experimental indications for a preferable combination of start-up plasma scenario and first wall materials. …”
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The quasi-continuous exhaust regime in JET by M. Faitsch, M. Dunne, E. Lerche, P. Lomas, I. Balboa, P. Bilkova, P. Bohm, A. Kappatou, D. Kos, B. Labit, S. Menmuir, O. Sauter, S. Silburn, E.R. Solano, H.J. Sun, A. Tookey, E. Viezzer, U. Stroth, JET Contributors, the EUROfusion Tokamak Exploitation Team

“…Porting the QCE regime to JET strongly benefited from the experimental and modelling efforts at the medium sized tokamaks ASDEX Upgrade and TCV. Using the physics picture developed from the ASDEX Upgrade experimental results, the route to the QCE regime in JET reported here is following closely the approach that was successful in ASDEX Upgrade. …”
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Doubling fusion power with volumetric optimization in magnetic confinement fusion devices by J. F. Parisi, J. W. Berkery, A. Sladkomedova, S. Guizzo, M. R. Hardman, J. R. Ball, A. O. Nelson, S. M. Kaye, M. Anastopoulos-Tzanis, S. A. M. McNamara, J. Dominski, S. Janhunen, M. Romanelli, D. Dickinson, A. Diallo, A. Dnestrovskii, W. Guttenfelder, C. Hansen, O. Myatra, H. R. Wilson

“…A technique, volumetric power optimization, is presented for enhancing the power output of magnetic confinement fusion devices. Applied to a tokamak, this approach involves shifting the burning plasma region to a larger plasma volume while introducing minimal perturbations to the plasma boundary shape. …”
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Development of a Remote Handling Robot for the Maintenance of an ITER-Like D-Shaped Vessel by Peihua Chen, Qixin Cao

“…Robotic operation is one of the major challenges in the remote maintenance of ITER vacuum vessel (VV) and future fusion reactors as inner operations of Tokamak have to be done by robots due to the internal adverse conditions. …”
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Estimation of neutral beam injector power transferred to KSTAR plasmas by Jong-Gu Kwak, J.H. Jeong, S.C. Hong

“…In a long pulse operation, the water coolant temperature is at the steady state condition in longer pulse more than 20s and the coupled neutral beam power to KSTAR plasma during the tokamak experiments is rechecked by using water flow calorimetric method after the experiment. …”
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Coil optimization methods for a planar coil stellarator by T.G. Kruger, M.F. Martin, D.A. Gates, the Thea Energy Team

“…The plasma encircling coils provide the mean magnetic field and linking current, similar to the toroidal field (TF) coils in a tokamak. The plasma encircling coils can be rotationally symmetric TF-like coils and produce a $B\propto 1/R$ field, but optimizing their placement, tilt, and shaping can substantially reduce the magnetic field error. …”
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Multiobjective Core Reloading Pattern Optimization of PARR-1 Using Modified Genetic Algorithm Coupled with Monte Carlo Methods by Nadeem Shaukat, Ammar Ahmad, Bukhtiar Mohsin, Rustam Khan, Salah Ud-Din Khan, Shahab Ud-Din Khan

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Development of Vacuum Vessel Design and Analysis Module for CFETR Integration Design Platform by Chen Zhu, Minyou Ye, Xufeng Liu, Shenji Wang, Shifeng Mao, Zhongwei Wang, Yi Yu

“…The integration engineering design platform aims at performing detailed engineering design for each tokamak component (e.g., breeding blanket, divertor, and vacuum vessel). …”
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