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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…
Advancements and Challenges in Nuclear Fusion Reactors Technology: A Comprehensive Overview
IntechOpen eBooksUntil now, the energy produced in nuclear reactors has come from the fission of heavy nuclei, particularly the isotope U-235. However, as is well known, the conversion of mass into energy also occurs with light nuclei. When hydrogen and deuterium fuse to fo…
Contour Optimization of High-Temperature Superconducting Toroidal Field Coils for Spherical Tokamaks
IEEE Transactions on Applied SuperconductivityHigh-temperature superconducting (HTS) spherical tokamaks face stringent space constraints, particularly at the inboard side, where excessive toroidal field (TF) coil inner-leg thickness limits space for other components like the central solenoid (CS) and s…
Modeling of the Sputtering Rate of the Tokamak First Wall by Atoms of Hydrogen Isotopes in the Near-Wall Plasma
Physics of Atomic NucleiAbstract A method for calculating sputtering of the tokamak first wall by fast charge-exchange neutral atoms of hydrogen isotopes in the near-wall plasma has been proposed. The application of the method has been shown by the example of sputtering of the ass…
Using deep learning for the detection of UFOs within the JET tokamak
Physics of PlasmasComponents on the inner wall of fusion reactors are exposed to extremely high heat loads, and significant care must be taken to minimize the damage to these components during operation. UFOs, also known as transient impurity events, are small particles of d…
Runaway electrons during a coil quench in stellarators
Physical Review AppliedIt is shown that avalanches of runaway electrons can arise in stellarators, even if there is no net toroidal current in the plasma or the magnetic-field coils, if the current in the latter varies rapidly enough, e.g., due to a superconductor quench. In pres…
Patent dataset in the field of nuclear fusion technology from 1955 to 2024
ScienceDBRetrieve nuclear fusion technology patent data and its citation data from the Incopat database. Based on the overall distribution of applications throughout the entire time period of the patent database and the time lag of patents, the retrieval time is lim…
Impact of lower hybrid current drive on edge velocity shear and turbulence in the HL-2A tokamak
Nuclear FusionAbstract The effect of lower hybrid current drive (LHCD) on edge velocity shear and turbulence in the HL-2A tokamak has been investigated. Experimental results demonstrate that the LHCD leads to an increase in edge velocity shear at both the inner and outer…
Physics drivers for the plasma-facing component design of the COMPASS-U tokamak
Plasma Physics and Controlled FusionAbstract The main drivers for the metallic plasma-facing component (PFC) design of the COMPASS Upgrade (COMPASS-U) tokamak ( B T ⩽ 5 T, I P ⩽ 2 MA, R geo = 0.9 m, a geo = 0.27 m, t flattop ⩽ 3 s) derived from physics considerations are presented in this pap…
Collisional-radiative data for tokamak disruption mitigation modeling
arXiv (Cornell University)Effective tokamak disruption mitigation is crucial for ensuring the safety and integrity of fusion power reactors. Accurate collisional-radiative (CR) modeling of a radiative plasma is a critical component in predictive disruption mitigation design. In this…
Efficient computation of the magnetic field created by a toroidal volumetric current of convex cross section with application to the study of the magnetic confinement in tokamaks
Computer Physics Communicationsnull
Thermo-structural assessment of the limiter inboard first wall design of the Divertor Tokamak Test facility
Fusion Engineering and DesignThe Divertor Tokamak Test facility (DTT) aims at investigating integrated power exhaust solutions that can be relevant for DEMO and future power plants. Such an ambitious goal imposes several constraints on the engineering design of the actively cooled plas…
Active ramp-down control and trajectory design for tokamaks with neural differential equations and reinforcement learning
Communications PhysicsThe tokamak offers a promising path to fusion energy, but disruptions pose a major economic risk, motivating solutions to manage their consequence. This work develops a reinforcement learning approach to this problem by training a policy to ramp-down the pl…
Plasma ejection phenomenon during non-inductive spherical tokamak start-up by ECH/ECCD on LATE
Plasma Physics and Controlled FusionAbstract The plasma ejection phenomenon that repeatedly occurs during non-inductive spherical tokamak start-up by electron cyclotron resonance heating and current drive (ECH/ECCD) on Low Aspect ratio Torus Experiment is reported. Measurements by interferome…
Overview of the studies towards a Plasma Position Reflectometry system for Divertor Test Tokamak (DTT)
Journal of InstrumentationAbstract Plasma Position Reflectometry (PPR) is taking an important role in next-generation fusion machines, such as DEMO, as a diagnostic to monitor the position and shape of the plasma, complementing magnetic diagnostics. The Divertor Test Tokamak (DTT) f…
Boundary plasma studies for a spherical tokamak with lithium walls
Nuclear Materials and EnergyBoundary plasma and plasma-material interactions are investigated for magnetised target fusion (MTF) applications. The General Fusion magnetised target fusion technology uses coaxial helicity injection (CHI) start-up which forms a spherical tokamak in a cav…
Design and calibration experiment of a two-photon absorption laser induced fluorescence diagnostic system for the Huanliu-3 tokamak
Review of Scientific InstrumentsA two-photon absorption laser induced fluorescence (TALIF) diagnostic system is designed for measuring the density of deuterium atoms in the scrape-off laser (SOL) region of the Huanliu-3 (HL-3) tokamak. The system employs laser pulses at 10 Hz with an ener…