A5068224789- Magnetic confinement fusion research
- Fusion materials and technologies
- Nuclear reactor physics and engineering
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Aerospace Engineering and Control Systems
- Particle Accelerators and Free-Electron Lasers
- Particle accelerators and beam dynamics
- Plasma Diagnostics and Applications
- Ionosphere and magnetosphere dynamics
- Radiative Heat Transfer Studies
- Electromagnetic Scattering and Analysis
- Fluid Dynamics and Turbulent Flows
- Advanced Surface Polishing Techniques
- Graphite, nuclear technology, radiation studies
- Radiation Effects in Electronics
- Experimental Learning in Engineering
- Nuclear Materials and Properties
Plasma Technology (United States)
2021-2024
Fusion Academy
2021-2023
Fusion (United States)
2021-2023
Massachusetts Institute of Technology
2023
University of York
2018-2020
University of Manchester
2015-2016
Abstract The MANTA (Modular Adjustable Negative Triangularity ARC-class) design study investigated how negative-triangularity (NT) may be leveraged in a compact, fusion pilot plant (FPP) to take ‘power-handling first’ approach. result is pulsed, radiative, ELM-free tokamak that satisfies and exceeds the FPP requirements described 2021 National Academies of Sciences, Engineering, Medicine (NASEM) report ‘Bringing Fusion U.S. Grid’ (2021 Bringing Grid ). A self-consistent integrated modeling...
Abstract This work explores detailed power handling solutions for a class of high-field, highly-radiative negative triangularity (NT) reactors based around the MANTA concept (Rutherford et al 2024 Plasma Phys. Control. Fusion ). The divertor design is kept as simple possible, opting standard with leg length. FreeGS used to create an equilibrium boundary region, prioritizing short outer length only ∼50 cm (∼40% minor radius). UEDGE code package plasma solution track temperatures and fluxes...
Abstract The separatrix operational space (SepOS) model [Eich \& Manz, \emph{Nuclear Fusion} (2021)] is shown to predict the L-H transition, L-mode density limit, and ideal MHD ballooning limit in terms of parameters for a wide range Alcator C-Mod plasmas. tested using Thomson scattering measurements across operating conditions on C-Mod, spanning $\overline{n}_{e} = 0.3 - 5.5 \times 10^{20}$m$^{-3}$, $B_{t} 2.5 8.0$ T, $B_{p} 0.1 1.2$ T. An empirical regression electron pressure gradient...
Abstract Extremely intense power exhaust channels are projected for tokamak-based fusion reactors; a means to handle them remains be demonstrated. Advanced divertor configurations have been proposed as potential solutions. Recent modelling of tightly baffled, long-legged geometries the test tokamak concept, ADX, has shown that these concepts may access passively stable, fully detached regimes over broad range parameters. The question how such divertors perform in reactor setting. To explore...
In this work, the UEDGE edge transport code is used to examine conditions in SPARC divertor and plasma for various levels of carbon impurity power from core (PSOL). A double-null magnetic configuration simulated assuming up-down symmetry geometry physics. The anomalous heat particle coefficients are tuned match empirical predictions SPARC's midplane density profiles, target plate flux inner/outer sharing. Convective included on low-field side, while high-field side modeled as purely...
Abstract In this work, we cross-compare the state-of-the-art edge plasma codes SOLPS-ITER, SOLEDGE2D, and UEDGE in a reactor-relevant neon-seeded Divertor Tokamak Test scenario at nominal power, extending simplified test-bed of Moscheni et al (2022 Nucl. Fusion 62 056009). Converged solutions targeting same separatrix density radiated power are obtained by adjusting pumping albedo neon puffing rate. This higher-power is generally characterised substantial disagreement between three codes, up...
Abstract Experimental measurements of plasma and neutral profiles across the pedestal are used in conjunction with 2D edge modeling to examine stiffness Alcator C-Mod H-mode plasmas. Enhanced D α experiments on observed degradation loss confinement below a critical value net power crossing separatrix, <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msub> <mml:mi>P</mml:mi> <mml:mi>net</mml:mi> </mml:mrow> </mml:msub> <mml:mo>=</mml:mo>...
Accurate modelling of the thermal transport in 'scrape-off-layer' (SOL) is great importance for assessing divertor exhaust power handling future high-power tokamak devices. In conditions low collisionality and/or steep temperature gradients that will be characteristic such devices, classical local diffusive theory breaks down, and becomes nonlocal, depending on distant regions plasma. An advanced nonlocal model implemented into a 1D SOL code 'SD1D' to create 'SD1D-nonlocal', study plasmas....
Abstract As reactor-level nuclear fusion experiments are approaching, a solution to the power exhaust issue in future reactors is still missing. The maximum steady-state heat load that can be exhausted by present technology around 10 MW m −2 . Different promising strategies aiming at successfully managing reactor-relevant conditions such limit not exceeded under investigation, and will tested Divertor Tokamak Test (DTT) experiment. Meanwhile, design of tokamaks beyond DTT, e.g. EU-DEMO/ARC,...
Abstract The design and understanding of alternative divertor configurations may be crucial for achieving acceptable steady-state heat particle material loads magnetic confinement fusion reactors. Multiple X-point geometries such as snowflakes targets have great potential in reducing power loads, but not yet been simulated widely codes with kinetic neutrals. This paper discusses recent changes made to the SOLPS-ITER code allow simulation target low-field side snowflake geometries. Snowflake...
The main goal of the Divertor Tokamak Test facility (DTT) is to operate with a high value power-exhaust-relevant parameter PSOL/R in plasma scenarios similar those foreseen for Demonstration Fusion Power Plant (DEMO) terms low collisionality and neutral opacity. For these unique characteristics, accurate modelling principal scenario necessary machine designing. In edge numerical codes, cross-field transport profiles have impact on results. This work aims at providing coherent set parameters...
Tokamak edge (scrape-off layer) plasmas can exhibit non-local transport in the direction parallel to magnetic field due steep temperature gradients. This effect along with its consequences has been explored at equilibrium for a range of conditions, from sheath-limited detached, using 1D kinetic electron code SOL-KiT, where electrons are treated kinetically and compared self-consistent fluid model. Line-averaged suppression heat flux (compared Spitzer-Harm) up 50% is observed, contrasting 98%...
Simulations of the ARC scrape-off layer and divertor configuration are carried out using UEDGE to perform first power-handling assessment for design. A convective–diffusive anomalous transport model is implemented in code reproduce radial plasma profiles anticipated device at outer mid-plane. Levels exhaust power from core varied, a 0.5% fixed fraction neon impurity seeding included investigations find steady-state detached solutions. Initial studies employing super-X have shown that stable...
This work explores power handling solutions for high-field, highly-radiative negative triangularity (NT) reactors based around the MANTA concept \cite{rutherford_manta_2024}. The divertor design is kept as simple possible, opting a standard with leg length. FreeGS used to create an equilibrium boundary region, prioritizing short outer length of only $\sim$50 cm ($\sim$40\% minor radius). UEDGE code package plasma solution, track temperatures and fluxes targets. It found that $P_\mathrm{SOL}$...
At the high $n_{e}$ proposed for high-field fusion reactors, it is uncertain whether ionization, as opposed to plasma transport, will be most influential in determining at pedestal and separatrix. A database of Alcator C-Mod discharges analyzed evaluate impact source modification via cryopumping. The contains similarly-shaped H-modes fixed $I_{p} =$ 0.8 MA $B_{t} 5.4 T, spanning a large range $P_\mathrm{net}$ ionization. Measurements from an edge Thomson Scattering system are combined with...
Plasma acceleration research station is an electron beam driven plasma wakefield test stand proposed for CLARA facility in Daresbury Laboratory. In this paper, the interaction between and numerically characterised via 2D numerical studies by using VSIM code. The wakefields induced a single bunch travelling through were found to vary from 200 MV/m 3 GV/m range of length, radius, densities. Energy gain particles populating tail head was demonstrated. After determining achievable field various...
PARS (Plasma Acceleration Research Station) is an electron beam driven plasma wakefield acceleration test stand proposed for VELA/CLARA facility in Daresbury Laboratory. In order to optimise various operational configurations, 2D numerical studies were performed by using VSIM a range of parameters such as bunch length, radius, density and positioning the bunches with respect each other two-beam scheme. this paper, some these considered measurement methods are presented.
PARS (Plasma Acceleration Research Station) is an electron beam driven plasma wakefield acceleration test stand proposed for VELA/CLARA facility in Daresbury Laboratory. In order to optimise various operational configurations, 2D numerical studies were performed by using VSIM a range of parameters such as bunch length, radius, density and positioning the bunches with respect each other two-beam scheme. this paper, some these considered measurement methods are presented.