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In-situ calibration of neutron flux monitor for HL-3 tokamak
Nuclear FusionAbstract This paper reports the rapid in-situ calibration of neutron flux monitors completed on the HL-3 tokamak device, a process that took only 14 h. The efficiency of the detection system, consisting of B-10 proportional counters and U-235 fission chambe…
Plasma-Facing Materials for Fusion Energy: Historical Review, Challenges and Future Directions
Extreme MaterialsThe promise of fusion energy is real. Major countries worldwide aim to achieve commercial grid-connected fusion power generation by around 2050, with magnetic confinement fusion—represented by tokamaks—leading the way among various fusion approaches. Howeve…
Study and analysis of ion cyclotron resonance heating scenarios for ADITYA-U Tokamak
Nuclear FusionAbstract This study provides a detailed analysis of ion cyclotron resonance heating (ICRH) scenarios for ADITYA-U Tokamak which is a crucial technique for core plasma heating in magnetically confined devices. The ICRH code LION is used to study the cyclotro…
Gyrokinetic simulations of magnetohydrodynamic modes in stellarator plasmas
Journal of Plasma PhysicsAbstract For small-shear helical-axis stellarators, linear ideal-magnetohydrodynamic (MHD) stability calculations and full-torus, nonlinear, electromagnetic gyrokinetic (GK) simulations (the latter with this unprecedented combination of objectives in stella…
Opportunities in pulsed magnetic fusion energy
Physics of PlasmasFusion is a potentially transformational energy technology, which promises limitless clean energy. Yet, it requires continued scientific and technological development to realize its potential. The conditions necessary for fusion energy gain in terms of the…
Preventing a Tokamak from Overheating
PhysicsPreventing a Tokamak from OverheatingFusion reactor experiments in Switzerland have demonstrated a new way to remove unwanted heat from a magnetically confined plasma. By Charles DayA mong the most enduring designs for a fusion reactor is the tokamak, which…
Demonstration of Super-X divertor exhaust control for transient heat load management in compact fusion reactors
Nature EnergyAbstract Nuclear fusion could offer clean, abundant energy. However, managing the power exhausted from the core fusion plasma towards the reactor wall remains a major challenge. This is compounded in emerging compact reactor designs promising more cost-effe…
Implementation of an ITER-relevant QP-based current limit avoidance algorithm in the TCV tokamak
Plasma Physics and Controlled FusionAbstract The problem of avoiding saturation of the coil currents is critical in large tokamaks with superconducting coils like ITER. Indeed, if the current limits are reached, a loss of control of the plasma may lead to a major disruption. Therefore, a curr…
Variety of coil sets for the compact stellarator-tokamak hybrid
Plasma Physics and Controlled FusionAbstract A first of-its-kind quasi-axisymmetric stellarator-tokamak hybrid design concept has recently been presented (Henneberg and Plunk 2024 Phys. Rev. Res. 6 L022052). Here we will provide an overview of various coil configurations that can be employed…
Preliminary measurements of alpha particles produced by proton-boron nuclear fusion reaction on Z-pinch type discharges
Plasma Physics and Controlled FusionAbstract The 11 B(p, α )2 α fusion reaction occurring in hydrogen-boron fuel seems to be the most promising, therefore it is currently being investigated in various systems such as magnetic confinement fusion, inertial confinement fusion, high-power lasers…
Turbulent Transport-Limited Pedestals in Tokamaks
arXiv (Cornell University)H-mode operation of tokamak fusion plasmas free of dangerous Type 1 edge-localized-modes (ELMs) requires a non-ELM mechanism for saturating the edge pedestal growth. One possible mechanism is turbulent transport. We introduce a transport threshold model to…
Impurity effects on the coupling of TEM and ITG mode in tokamak deuterium–tritium mixture plasmas
Physics of PlasmasThe gyrokinetic integral eigenvalue equation is extended to include the mixing of hydrogen isotopes, deuterium and tritium ions, as the main ion species. Impurity effects on the coupling of the trapped electron mode (TEM) and ion temperature gradient (ITG)…
Combining physics-based and data-driven models for quantitatively accurate plasma profile prediction that extrapolates well; with application to DIII-D, AUG, and ITER tokamaks
Nuclear FusionAbstract For design, scenario planning, and control, ITER and all other envisioned tokamaks rely on a variety of statistical and physics-based models to extrapolate to unseen regimes; most notably from low plasma current to high. A ‘meta-learning’ methodolo…
Surface loss probabilities of boron-hydride radicals in W7-X and ASDEX Upgrade
Nuclear Materials and Energy• The surface loss probabilities of boron hydride radicals created in boronisation plasmas in W7-X and ASDEX Upgrade were determined experimentally using the cavity technique. • The incident flux responsible for the growth of boron layers consists predomina…
Simulation of fusion neutron spectra from D-D and D-T thermonuclear fusion
Scientific ReportsInvestigating the neutron spectra produced by thermonuclear fusion reactions D(d , n) 3 He and T(d , n) 4 He , which will power the future fusion reactors, is a critical factor in improving the performance of fusion reactors. Experimentally, it is extremely…
Offline Reinforcement Learning for Rotation Profile Control in Tokamaks
arXiv (Cornell University)Tokamaks remain leading candidates for achieving practical fusion energy, yet many important control problems inside these devices are still difficult or unsolved. One such challenge is controlling the plasma rotation profile, which strongly influences stab…
Core-edge integrated predictive studies of ST40 and NSTX plasmas with the scrape-off layer box model
Physics of PlasmasThe ability to model the interplay between the core and edge of tokamak plasmas is crucial to designing both the plasma operating scenario of a fusion pilot plant and the design of the tokamak itself. Scrape-off-layer (SOL) models that are tailored to integ…
Preliminary machine learning-based calibration strategy for the ITER Tokamak Systems Monitor
Fusion Engineering and DesignA machine learning-based calibration strategy for the ITER Tokamak Systems Monitor (TSM) is presented, focusing on the optimization of dynamic finite-element method (FEM) models essential for monitoring and assessing the structural health of the tokamak. Tr…
Optimized finite-$β$ tokamak-stellarator hybrid configurations achieved by planar dipole-field coils
arXiv (Cornell University)Tokamak--stellarator hybrids seek to combine tokamak-like compactness and confinement with stellarator-like externally generated rotational transform and steady-state operation. In this work, we build on the recent tokamak--stellarator hybrid study using pl…
Evaluation of charged-particle stopping models for fusion plasmas
Plasma Physics and Controlled FusionAbstract Accurate prediction of alpha particle stopping powers in a laser-induced plasma is critical for inertial confinement fusion (ICF) and magnetic fusion energy research. This study presents a comprehensive comparison of four distinct approaches: the n…
High Field Diamond Magnetometry Towards Tokamak Diagnostics
arXiv (Cornell University)Nitrogen vacancy centres (NVC) in diamond have been widely used for near-dc magnetometry. The intrinsic properties of diamonds make them potential candidates for tokamak fusion power diagnostics, where radiation-hard magnetometers will be essential for effi…
Edge-localized mode mitigation enabled by active control of pedestal density gradient with new EAST tokamak divertor
Physics of PlasmasMitigation of large edge-localized modes (ELMs) has been achieved by actively reducing the pedestal density gradient with the EAST new right-angled lower divertor through changing the strike point position from the vertical target to the horizontal target.…
21.7-T Large-Scale High-Temperature Superconducting Toroidal Magnet for Tokamak Fusion Application
IEEE Transactions on Applied SuperconductivityWith the rapid advancement of magnetic confinement fusion technology, High- Temperature Superconductors (HTS) have emerged as a cornerstone for compact and efficient tokamak systems due to their exceptional current-carrying capacity under high magnetic fiel…
Evaluation of neoclassical transport in nearly quasi-isodynamic stellarator magnetic fields using MONKES
Nuclear FusionAbstract Stellarator magnetic fields that are perfectly optimized for neoclassical transport (with levels of radial neoclassical transport comparable to tokamaks) are called omnigenous. Quasi-isodynamic (QI) magnetic fields are a subset of omnigenous magnet…