F. Turco
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View article: Identification and control of the exhaust using gas perturbations in the DIII-D tokamak
Identification and control of the exhaust using gas perturbations in the DIII-D tokamak Open
This paper presents perturbative experiments that enable the validation and development of control-oriented models for exhaust control. We identify the response of the divertor plasma and scrape-off layer in the DIII-D tokamak to deuterium…
View article: Technology readiness assessment of magnetohydrodynamic stability control
Technology readiness assessment of magnetohydrodynamic stability control Open
The technology readiness level scale is revised with clear definitions for magnetohydrodynamic stability control technologies for magnetic confinement fusion. The definitions are in the form of a sentence with three dimensions, which are t…
View article: The new ITER baseline, research plan and open R&D issues
The new ITER baseline, research plan and open R&D issues Open
A new baseline (NB) has been proposed by the ITER Project to ensure a robust achievement of the Projects’ goals, in view of past challenges including delays incurred due to the Covid-19 pandemic, technical challenges in completing first-of…
View article: Pedestal formation via different trajectories in the stability space in response to the timing scan of neutral beam heating in DIII-D
Pedestal formation via different trajectories in the stability space in response to the timing scan of neutral beam heating in DIII-D Open
The frequency of type-I ELMs decreases as the initiation of the neutral beam injection (NBI) heating is delayed with respect to the time when plasma current (Ip) reaches flat-top in the ITER Baseline Scenario discharges in DIII-D. Hencefor…
View article: Novel intrinsic helical cores and MHD dynamo flux pumping evidence in DIII-D
Novel intrinsic helical cores and MHD dynamo flux pumping evidence in DIII-D Open
Evidence of a MHD dynamo brought about by intrinsic helical core structures in negative triangularity (NT) and ITER baseline scenario (IBS) plasmas demonstrates paths to operating tokamaks without seeds for deleterious global MHD modes. A …
View article: Radiation induced non-linear oscillations in ITER baseline scenario plasmas in DIII-D
Radiation induced non-linear oscillations in ITER baseline scenario plasmas in DIII-D Open
This work shows how the radiation brought about by metals or metal-equivalent radiators such as Kr and Xe produces non-linear dynamics on otherwise stationary β N flattops of DIII-D ITER Baseline Scenario demonstration discharges. The Kr a…
View article: First tungsten radiation studies in DIII-D’s ITER baseline demonstration discharges
First tungsten radiation studies in DIII-D’s ITER baseline demonstration discharges Open
ITER Baseline Scenario plasmas were studied in DIII-D using krypton and xenon gases as a proxy for the tungsten that will be present in ITER. These impurities were chosen for having the same radiative loss rate Lz as tungsten would exhibit…
View article: Modelling and experiment to stabilize disruptive tearing modes in the ITER baseline scenario in DIII-D
Modelling and experiment to stabilize disruptive tearing modes in the ITER baseline scenario in DIII-D Open
The achievement of high gain, stationary conditions in a tokamak scenario aimed at producing fusion energy in the ITER Project is crucial to the demonstration that this form of energy can be used in future reactors to provide cheap and cle…
View article: Power and isotope effects in the ITER baseline scenario with tungsten and tungsten-equivalent radiators in DIII-D
Power and isotope effects in the ITER baseline scenario with tungsten and tungsten-equivalent radiators in DIII-D Open
Experiments in DIII-D document the ITER Baseline Scenario (IBS) at q 95 ∼ 3 and P IN / P LH ∼ 1–2, in both deuterium and hydrogen utilizing Kr and Xe as Tungsten-equivalent radiators. The power threshold for H-mode operation ( P LH ) was d…
View article: MHD stability of negative triangularity DIII-D plasmas
MHD stability of negative triangularity DIII-D plasmas Open
Negative triangularity (NT) experiments in DIII-D point to an emergent reactor scenario free of sawteeth, endowed with benign, nondisruptive n = 2 tearing modes, which experience q min 1 similar to the positive triangularity hybrid scen…
View article: Simultaneous stabilization and control of the n = 1 and n = 2 resistive wall mode
Simultaneous stabilization and control of the n = 1 and n = 2 resistive wall mode Open
DIII-D experiments demonstrate simultaneous stability measurements and control of resistive wall modes (RWMs) with toroidal mode numbers n = 1 and n = 2. RWMs with n > 1 are sometimes observed on DIII-D following the successful feedback st…
View article: The physics basis to integrate an MHD stable, high-power hybrid scenario to a cool divertor for steady-state reactor operation
The physics basis to integrate an MHD stable, high-power hybrid scenario to a cool divertor for steady-state reactor operation Open
Coupling a high-performance core to a low heat flux divertor is a crucial step for ITER and a Fusion Pilot Plant or DEMO. Experiments in DIII-D recently expanded the steady-state hybrid scenario to high density and divertor impurity inject…
View article: Studies of EC pre-ionization in DIII-D to support development of ITER plasma initiation
Studies of EC pre-ionization in DIII-D to support development of ITER plasma initiation Open
New experiments have been conducted at DIII-D to improve the physics understanding of plasma initiation assisted by electron cyclotron (EC) wave injection, allowing better extrapolation to ITER. This has been achieved by applying an EC pul…
View article: Diverted negative triangularity plasmas on DIII-D: the benefit of high confinement without the liability of an edge pedestal
Diverted negative triangularity plasmas on DIII-D: the benefit of high confinement without the liability of an edge pedestal Open
Diverted discharges at negative triangularity on the DIII-D tokamak sustain normalized confinement and pressure levels typical of standard H-mode scenarios (H98y,2≅1, βN≅3) without developing an edge pressure pedestal, despite the auxiliar…
View article: Resistive contributions to the stability of DIII-D ITER baseline demonstration discharges
Resistive contributions to the stability of DIII-D ITER baseline demonstration discharges Open
Measurements of the plasma response to applied n = 1 perturbations from DIII-D ITER baseline scenario (IBS) demonstration discharges exhibit increasing amplitude prior to disruption inducing mode locking events. Simulations reveal that cha…
View article: Response of thermal and fast-ion transport to beam ion population, rotation and T <sub>e</sub>/T <sub>i</sub> in the DIII-D steady state hybrid scenario
Response of thermal and fast-ion transport to beam ion population, rotation and T <sub>e</sub>/T <sub>i</sub> in the DIII-D steady state hybrid scenario Open
The thermal and fast-ion transport properties of DIII-D steady-state hybrid discharges with normalized beta β N ≳ 3 are studied at low injected torque and an increased electron to ion temperature ratio T e / T i . Linear stability analysis…
View article: First Evidence of Local <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" display="inline"><mml:mi mathvariant="bold">E</mml:mi><mml:mo>×</mml:mo><mml:mi mathvariant="bold">B</mml:mi></mml:math> Drift in the Divertor Influencing the Structure and Stability of Confined Plasma near the Edge of Fusion Devices
First Evidence of Local Drift in the Divertor Influencing the Structure and Stability of Confined Plasma near the Edge of Fusion Devices Open
The structure of the edge plasma in a magnetic confinement system has a strong impact on the overall plasma performance. We uncover for the first time a magnetic-field-direction dependent density shelf, i.e., local flattening of the densit…
View article: Cause and impact of low-frequency chirping modes in DIII-D hybrid discharges
Cause and impact of low-frequency chirping modes in DIII-D hybrid discharges Open
Significant variations in MHD activity and fast-ion transport are observed in the DIII-D high-beta, steady-state hybrid discharges with a mixture of electron cyclotron (EC) waves and neutral beam injection (NBI). When electron cyclotron he…
View article: High performance double-null plasmas under radiating divertor and mantle scenarios on DIII-D
High performance double-null plasmas under radiating divertor and mantle scenarios on DIII-D Open
Experiments to combine a radiating divertor or mantle with high power, high βN plasma operation have successfully reduced the divertor heat flux by 40% but have also encountered several challenging problems. For example, injecting either n…
View article: Progress in disruption prevention for ITER
Progress in disruption prevention for ITER Open
Key plasma physics and real-time control elements needed for robustly stable operation of high fusion power discharges in ITER have been shown in recent research worldwide. Recent analysis has identified the current density profile as the …
View article: Hybrid simulations of fishbone instabilities and Alfvén eigenmodes in DIII-D tokamak
Hybrid simulations of fishbone instabilities and Alfvén eigenmodes in DIII-D tokamak Open
In DIII-D hybrid discharges, the intense Alfvén eigenmode (AE) activity driven by Neutral Beam Injection that is typically observed can be suppressed and replaced by fishbone modes when Electron Cyclotron Current Drive (ECCD) is centrally …
View article: Assessment of the baseline scenario at<i>q</i><sub>95</sub>~ 3 for ITER
Assessment of the baseline scenario at<i>q</i><sub>95</sub>~ 3 for ITER Open
The International Tokamak Physics Activity topical group on integrated operational scenarios has compiled a database of stationary H-mode discharges at q(95) similar to 3 from AUG, C-Mod, DIII-D, JET and JT-60U, for both carbon wall and hi…
View article: The causes of the disruptive tearing instabilities of the ITER Baseline Scenario in DIII-D
The causes of the disruptive tearing instabilities of the ITER Baseline Scenario in DIII-D Open
Analysis of the evolving current density (J), pedestal and rotation profiles in a database of 200 ITER Baseline Scenario (IBS) demonstration discharges in the DIII-D tokamak identifies the current profile as a key determinant of the disrup…
View article: Grassy-ELM regime with edge resonant magnetic perturbations in fully noninductive plasmas in the DIII-D tokamak
Grassy-ELM regime with edge resonant magnetic perturbations in fully noninductive plasmas in the DIII-D tokamak Open
Resonant magnetic perturbations (n=3 RMPs) are used to eliminate large amplitude ELMs and reduce the amplitude of weaker "grassy"-ELMs in DIII-D plasmas relevant to the ITER steady-state mission. Fully non-inductive discharges in the ITER …
View article: On Principles, Values, Metrics and Criteria for the Development of Magnetic Fusion Energy
On Principles, Values, Metrics and Criteria for the Development of Magnetic Fusion Energy Open
Fusion energy holds the promise of providing abundant, safe, clean and environmentally sustainable power for the foreseeable future. Hence, fusion has enormous potential to benefit society if it can be developed into a commercial energy so…
View article: Advances in the steady-state hybrid regime in DIII-D—a fully non-inductive, ELM-suppressed scenario for ITER
Advances in the steady-state hybrid regime in DIII-D—a fully non-inductive, ELM-suppressed scenario for ITER Open
Here, the hybrid regime with beta, collisionality, safety factor and plasma shape relevant to the ITER steady-state mission has been successfully integrated with ELM suppression by applying an odd parity n=3 resonant magnetic perturbation …
View article: Helical core reconstruction of a DIII-D hybrid scenario tokamak discharge
Helical core reconstruction of a DIII-D hybrid scenario tokamak discharge Open
Our paper presents the first fully 3-dimensional (3D) equilibrium reconstruction of a helical core in a tokamak device. Using a new parallel implementation of the Variational Moments Equilibrium Code (PARVMEC) coupled to V3FIT, 3D reconstr…
View article: Improved confinement in highly powered high performance scenarios on DIII-D
Improved confinement in highly powered high performance scenarios on DIII-D Open
DIII-D has recently shown improved energy confinement by injecting neutral deuterium gas into high performance near-double null divertor (DND) plasmas during high power operation. Representative parameters for these plasmas are: q 95 = 6, …
View article: Role of a continuous MHD dynamo in the formation of 3D equilibria in fusion plasmas
Role of a continuous MHD dynamo in the formation of 3D equilibria in fusion plasmas Open
Stationary 3D equilibria can form in fusion plasmas via saturation of magnetohydrodynamic (MHD) instabilities or stimulated by external 3D fields. In these cases the current profile is anomalously broad due to magnetic flux pumping produce…