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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…
The implications of impurities on shutdown dose rates in the burning plasma experimental tokamak
Fusion Engineering and Designnull
INFLUENCE OF DRIFTS AND CURRENTS ON THE MAIN OPERATING PARAMETERS OF THE TOKAMAK T-15MD DIVERTOR
Физика плазмыThe work presents the results of the first calculations of the T-15MD tokamak near-wall plasma in the SOLPS-ITER code taking into account the effects of drifts and currents. The modes with the power passing through the separatrix PSOL = 6 MW and different H…
Composition of electron temperature gradient driven plasma turbulence in JET-ILW tokamak plasmas
Physical Review ResearchThis letter reports on new fundamental insights into small scale plasma turbulence that is responsible for confinement degradation on the JET tokamak. We compare the structure of electron temperature gradient (ETG) driven turbulence in the edge region of tw…
Design of an Equiangular Spiral Antenna for Efficiency Enhancement in Tokamak for Fusion Reactors
Springer proceedings in physicsnull
Self-consistent modeling of tokamak edge plasma transport with lithium sources
Physics of PlasmasMagnetic confinement fusion devices require effective heat and particle exhaust solutions on the divertor plates to operate sustainably, especially under reactor-relevant conditions. Liquid lithium divertors have been proposed to address two major challenge…
Integrated modeling of RF-induced tungsten erosion at ICRH antenna structures in the WEST tokamak *
Nuclear FusionAbstract This paper introduces STRIPE (Simulated Transport of RF Impurity Production and Emission), an advanced modeling framework developed to analyze material erosion and the global transport of eroded impurities originating from radio-frequency (RF) ante…
Cryodistribution System for Superconducting Tokamak Magnets
IEEE Transactions on Applied SuperconductivityThe ITER Tokamak, equipped with large-scale superconducting (SC) magnets, requires cryogenic conditions sustained by helium coolant. The operation of these magnets presents significant challenges from the perspective of the helium cryogenic system. These ch…
Connecting recent JET isotope L–H transition studies to H-mode access in new ITER scenarios
Plasma Physics and Controlled FusionAbstract This paper reviews recent experimental advances in characterising the low-to-high confinement mode (L–H) transition in tokamaks, with a particular focus on ITER-relevant results from JET and metallic wall tokamaks. Achieving H-mode is critical for…
Macroscopic trends of neoclassical tearing stability in high-field H-mode tokamak pilot plants
Nuclear FusionAbstract The neoclassical tearing mode (NTM) stability metric—minimum marginally stable island width w m ∗ —was compared across 14651 inductive high-field tokamak pilot plant equilibria. Larger devices with reduced elongation and/or increased minor radius d…
Public Data Set: Operation of the Pegasus-III Spherical Tokamak for Non-Solenoidal Startup Development
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)This public dataset contains openly-documented, machine readable digital research data corresponding to figures published in M.D. Nornberg et al., "Operation of the Pegasus-III Spherical Tokamak for Non-Solenoidal Startup Development," accepted for publicat…
Application of ECWR for tin removal with prospective use in tokamaks with liquid metal divertor
Plasma Physics and Controlled FusionAbstract One of the problems of the liquid metal tokamak divertor technology is the redeposition of the released metal on the tokamak vessel walls. In this work an investigation of the removal of the redeposited metals from grounded conducting walls of toka…
Modelling of shattered pellet injection experiments on the ASDEX Upgrade tokamak
Nuclear FusionAbstract In a shattered pellet injection (SPI) system the penetration and assimilation of the injected material depends on the speed and size distribution of the SPI fragments. ASDEX Upgrade (AUG) was recently equipped with a flexible SPI to study the effec…
Commissioning of the Power Supplies and Coils of the SMART Tokamak
IEEE Transactions on Plasma ScienceThe small aspect ratio tokamak (SMART) is a spherical tokamak (ST) that offers unique capabilities for studying the potential of negative triangularity. It has been designed, constructed, and is currently being operated by the Plasma Science Fusion Technolo…
Progress and innovations in the TCV tokamak research programme
Nuclear FusionAbstract Research on the Tokamak à Configuration Variable addresses a wide range of key questions relevant to ITER and future fusion power plants. Over the past two years, highly productive experimental campaigns have led to major advances across several ar…
Fast-ion phase-space tomography with wave–particle interactions in the ion cyclotron frequency range as prior
Nuclear FusionAbstract The fast-ion distribution function in fusion plasmas can be inferred by inverting Doppler-shifted measurements from fast-ion diagnostics. The full fast-ion distribution function can be parametrised by three constants of motion with the addition of…
Neutral beam integrated efficiency for steady-state operation of a fusion neutron source design based on a spherical tokamak
Plasma Physics and Controlled FusionAbstract High fusion performance and steady-state plasma operation are the key challenges for designing a compact fusion neutron source based on a spherical tokamak. Steady-state operation will be supported by non-inductive current drive (NBCD) produced by…