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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…
A novel reciprocating probe design for ion temperature measurements at the WEST tokamak lower divertor
Measurement Science and TechnologyAbstract A reciprocating retarding field analyzer has been installed in the lower divertor of the WEST tokamak to measure the local ion temperature in ITER-like tungsten divertor conditions. The paper presents the design of the analyzer, the robust magnetic…
Machine learning based energy confinement time extrapolation via multi-tokamak database
Fusion Engineering and DesignPredicting energy confinement time in future fusion devices like ITER is a significant challenge for traditional methods. This study introduces an advanced machine learning framework to address this. Our approach utilizes deep ensembles for robust uncertain…
Simultaneous two-dimensional measurement of plasma density and electron temperature evolution via multi-color gas puff imaging on the HL-3 tokamak
Review of Scientific InstrumentsA Multi-Color Gas Puff Imaging (MC-GPI) diagnostic system has been implemented on the HL-3 tokamak, employing a helium line intensity ratio methodology for simultaneous two-dimensional (2D) measurements of plasma density and electron temperature. The system…
Fusion research in a Deuterium-Tritium tokamak
Fundamental Plasma PhysicsThe recent ITER re-baselining calls for new fusion-relevant research best carried out in a DT-capable tokamak device with similar technical choices. The present paper describes key issues that could be addressed in a Suitably Enhanced DT-capable Tokamak (SE…
Sawtooth crash in tokamak as a sequence of Multi-region Relaxed MHD equilibria
arXivThis study examines the sawtooth crash phenomenon in tokamak plasmas by modelling it as a sequence of Multi-region Relaxed Magnetohydrodynamic (MRxMHD) equilibria. Using the Stepped-Pressure Equilibrium Code (SPEC), we constructed a series of equilibria rep…
Bayesian optimization for design space exploration of tokamak fusion reactors
SSRN Electronic Journalnull
Investigation of the effects of transient heat loads on plasma-facing materials in Tokamaks
arXiv (Cornell University)Nuclear fusion devices are constantly under the threat of malfunctions coming from the damages of plasma-facing materials due to being affected by thermal heat loads. The frequent heat loads during some transient events in large-scale Tokamaks have always b…
TRANSP integrated modeling code for interpretive and predictive analysis of tokamak plasmas
Computer Physics CommunicationsThis paper provides a comprehensive review of the TRANSP code, a sophisticated tool for interpretive and predictive analysis of tokamak plasmas, detailing its major capabilities and features. It describes the equations for particle, power, and momentum bala…