O. Schmitz

ORCID: 0000-0002-9580-9149
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About
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Research Areas
  • Magnetic confinement fusion research
  • Fusion materials and technologies
  • Ionosphere and magnetosphere dynamics
  • Laser-Plasma Interactions and Diagnostics
  • Superconducting Materials and Applications
  • Plasma Diagnostics and Applications
  • Particle accelerators and beam dynamics
  • Nuclear reactor physics and engineering
  • Laser-induced spectroscopy and plasma
  • Atomic and Molecular Physics
  • Solar and Space Plasma Dynamics
  • Particle Accelerators and Free-Electron Lasers
  • Nuclear Materials and Properties
  • Nuclear Physics and Applications
  • Atomic and Subatomic Physics Research
  • Astro and Planetary Science
  • Radio Frequency Integrated Circuit Design
  • Astronomical Observations and Instrumentation
  • Antenna Design and Analysis
  • Gas Dynamics and Kinetic Theory
  • Diamond and Carbon-based Materials Research
  • Microwave Engineering and Waveguides
  • Spacecraft and Cryogenic Technologies
  • Metal and Thin Film Mechanics
  • Advanced Antenna and Metasurface Technologies

University of Wisconsin–Madison
2016-2025

Max Planck Institute for Plasma Physics
2014-2024

Max Planck Institute for Plasma Physics - Greifswald
2016-2023

Campbell Collaboration
2020-2022

University of Wisconsin System
2021

Universitat Politècnica de Catalunya
2019

Barcelona Supercomputing Center
2019

Max Planck Society
2014-2018

National Agency for New Technologies, Energy and Sustainable Economic Development
2016

University of Padua
2016

• Reviews the fundamental physics aspects of first ITER W divertor and defines required operational lifetime within Staged Approach. Uses SOLPS simulation database to establish target peak heat flux neutral pressure burning plasma operating domain. Assesses consequences narrow SOL channels, fluid drifts, component shaping 3D magnetic fields for ELM control. recrystallization define an budget shows that fluxes ∼50% higher than previously assumed may be acceptable. Shows Ne N should equally...

10.1016/j.nme.2019.100696 article EN cc-by-nc-nd Nuclear Materials and Energy 2019-07-18

Large Type-I edge localized modes (ELMs) are completely eliminated with small n = 3 resonant magnetic perturbations (RMP) in low average triangularity, , plasmas and ITER similar shaped (ISS) plasmas, relevant collisionalities . Significant differences the RMP requirements properties of ELM suppressed found when comparing two triangularities. In ISS current required to suppress ELMs is approximately 25% higher than triangularity plasmas. It also that width q95 window for suppression smaller...

10.1088/0029-5515/48/2/024002 article EN Nuclear Fusion 2008-01-23

Progress in the definition of requirements for edge localized mode (ELM) control and application ELM methods both high fusion performance DT operation non-active low-current ITER is described. Evaluation power fluxes low plasma current H-modes shows that uncontrolled ELMs will not lead to damage tungsten (W) divertor target, unlike high-current which by expected. Despite lack at lower currents, found be required under these conditions prevent an excessive contamination W, could eventually...

10.1088/0029-5515/54/3/033007 article EN Nuclear Fusion 2014-02-20

The EPED model predicts the H-mode pedestal height and width based upon two fundamental calculable constraints: (1) onset of non-local peeling-ballooning modes at low to intermediate mode number, (2) nearly local kinetic ballooning high number. We present detailed tests in discharges with edge localized (ELMs), employing new resolution measurements, finding good quantitative agreement across a range parameters. is then applied for first time quiescent (QH), similar level between predicted...

10.1063/1.3699623 article EN Physics of Plasmas 2012-04-06

In this paper the manipulation of power deposition on divertor targets at DIII-D by application resonant magnetic perturbations (RMPs) for suppression large type-I edge localized modes (ELMs) is analysed. We discuss modification ELM characteristics RMP applied. It shown that width pattern in ELMy H-mode depends linearly deposited energy, whereas phase discharge those patterns are controlled externally induced perturbation. was also found heat transport due to small, plasma pedestal electron...

10.1088/0029-5515/49/9/095013 article EN Nuclear Fusion 2009-08-14

Recent DIII-D [J. L. Luxon et al., Nucl. Fusion 43, 1813 (2003)] experiments show a correlation between the extent of overlap magnetic islands induced in edge plasma by perturbation coils and complete suppression Type-I localized modes (ELMs) plasmas with ITER-like electron pedestal collisionality νe*∼0.1, flux surface shape low safety factor (q95≈3.6). With fixed amplitude n=3 resonant (RMP), ELM is obtained only finite window (q95) consistent maximizing component applied helical field....

10.1063/1.2901064 article EN Physics of Plasmas 2008-05-01

Operating ITER in the reference inductive scenario at design values of Ip = 15 MA and QDT 10 requires achievement good H-mode confinement that relies on presence an edge transport barrier whose pedestal pressure height is key to plasma performance. Strong gradients occur such conditions can drive magnetohydrodynamic instabilities resulting localized modes (ELMs), which produce a rapid energy loss from region facing components (PFC). Without appropriate control, heat loads PFCs during ELMs...

10.1088/0029-5515/53/4/043004 article EN Nuclear Fusion 2013-03-06

Abstract The non-linear reduced four-field RMHD model in cylindrical geometry was extended to include plasma rotation, neoclassical poloidal viscosity and two fluid diamagnetic effects. Interaction of the static resonant magnetic perturbations (RMPs) with rotating plasmas tokamaks studied. self-consistent evolution equilibrium electric field due RMP penetration is taken into account model. It demonstrated that pedestal region steep pressure gradients, mean flows perpendicular field, which...

10.1088/0029-5515/52/5/054003 article EN Nuclear Fusion 2012-05-01

Abstract The EMC3‐Eirene code is improved in many aspects. Ad hoc boundary conditions for intrinsic impurities at the SOL‐core interface are removed by implicitly coupling to a 1D core model. Non‐uniform cross‐field transport coefficients allowed new version. A particle splitting technique implemented improving Monte Carlo statistic low‐temperature ranges of most interest. Domain splitting, which was possible toroidal direction only, now feasible all three directions, facilitating mesh...

10.1002/ctpp.201410092 article EN Contributions to Plasma Physics 2014-06-01

The Wisconsin high-temperature superconductor axisymmetric mirror experiment (WHAM) will be a high-field platform for prototyping technologies, validating interchange stabilization techniques and benchmarking numerical code performance, enabling the next step up to reactor parameters. A detailed overview of experimental apparatus its various subsystems is presented. WHAM use electron cyclotron heating ionize build dense target plasma neutral beam injection fast ions, stabilized by...

10.1017/s0022377823000806 article EN cc-by Journal of Plasma Physics 2023-09-20

Abstract Resilient divertor features connected to open chaotic edge structures in the Helically Symmetric eXperiment are investigated. For first time, an expanded vessel wall was considered that would give space for implementation of a physical target structure. The analysis done four different magnetic configurations with very plasma edges. A resilient interaction pattern identified across all configurations. This manifests as qualitatively similar footprint behavior equilibria. Overall,...

10.1088/1361-6587/adb179 article EN cc-by Plasma Physics and Controlled Fusion 2025-02-03

Abstract Since the publication of review Progress in ITER Physics Basis (PIPB) 2007, significant progress has been made understanding processes at plasma-material interface. This review, part ITPA Nuclear Fusion Special Issue On Path to Burning Plasma Operation , presents these developments, focusing on key areas such as physics plasma exhaust, interactions, and properties plasma-facing materials their evolution under exposure. The coordinated efforts Topical Group Scrape-Off Layer Divertor...

10.1088/1741-4326/adaf42 article EN cc-by Nuclear Fusion 2025-03-10

A study of three-dimensional (3D) perturbed magnetic field structures and transport for edge localized mode control experiments with resonant perturbations at DIII-D is presented. We focus on ITER-Similar Shape plasmas ITER relevant electron pedestal collisionalities . This performed in comparison results from TEXTOR-Dynamic Ergodic Divertor circular limiter plasmas. For both the structure analyzed vacuum paradigm—superimposing external RMP unperturbed equilibrium. TEXTOR L-mode this...

10.1088/0741-3335/50/12/124029 article EN Plasma Physics and Controlled Fusion 2008-11-04

A comprehensive set of L–H transition experiments has been performed on DIII-D to determine the requirements for access H-mode plasmas in ITER's first (non-nuclear) operational phase with H and He second (activated) D plasmas. The power threshold, P TH , was evaluated different configurations auxiliary heating methods main ion species. Helium have significantly higher than deuterium at low densities all schemes, but similar as high except H-neutral beam injection-heated discharges, which are...

10.1088/0029-5515/51/10/103020 article EN Nuclear Fusion 2011-08-31

Recent experiments on JET have shown that type-I edge localized modes (ELMs) can be controlled by the application of static low n = 1 external magnetic perturbation fields produced four error field correction coils (EFCC) mounted far away from plasma between transformer limbs. When an with amplitude a few mT at (the normalized poloidal flux, ?, is larger than 0.95) applied during stationary phase ELMy H-mode plasma, ELM frequency rises ~30?Hz up to ~120?Hz. The energy loss per total stored...

10.1088/0029-5515/50/2/025013 article EN Nuclear Fusion 2010-01-15

A detailed experiment-theory comparison reveals that linear ideal MHD theory is in quantitative agreement with external magnetic and internal soft x-ray measurements of the plasma response to externally applied non-axisymmetric fields over a broad range beta rotation. This result represents significant step toward goal advancing understanding three-dimensional tokamak equilibria. Both show driven perturbation increases linearly perturbation, suggesting relevance models. The are made at...

10.1063/1.3593009 article EN Physics of Plasmas 2011-05-01

Long-wavelength turbulence increases dramatically in the outer regions of DIII-D plasmas with application resonant magnetic field perturbations (RMPs) that suppress edge-localized modes (ELMs). Correspondingly, transport and global energy confinement decreases these low-collisionality RMP-ELM suppressed discharges. The core pedestal density are sharply reduced, while ion electron temperatures may change only slightly. Low wavenumber (k⊥ρi < 1) range 60–300 kHz, measured beam emission...

10.1088/0029-5515/53/11/113011 article EN Nuclear Fusion 2013-09-23

In-vessel, non-axisymmetric, control coils have proven to be an important option for mitigating and suppressing edge-localized modes (ELMs) in high performance operating regimes on a growing number of tokamaks. Additionally, in-vessel non-axisymmetric ELM coil is being considered the ITER baseline design. In preparing initial operation this set, comprehensive study was carried out characterize linear superposition 3D vacuum magnetic field, produced by coil, series equilibria representing...

10.1088/0029-5515/53/9/093029 article EN Nuclear Fusion 2013-08-29

Wendelstein 7-X (W7-X) is currently under commissioning in preparation for its initial plasma operation phase, phase 1.1 (OP1.1). This first serves primarily to provide an integral of all major systems needed operation, as well systems, such diagnostics, that need verify their foreseen functions. In OP1.1, W7-X will have a reduced set in-vessel components. particular, five graphite limiter stripes replace the later divertor. paper describes expected machine capabilities selection physics...

10.1088/0029-5515/55/12/126001 article EN Nuclear Fusion 2015-11-01

Abstract The fundamental behavior of the W7-X island divertor under detached conditions, which has been theoretically predicted with EMC3-Eirene code, is re-examined here experimental conditions achieved so far and compared first results. Both simulations experiments cover a range configurations plasma parameters, show following common trends: (1) rising impurity radiation, target heat load decreases ‘uniformly’ over entire surface in sense that both peak average loads can drop by an order...

10.1088/1741-4326/ac0772 article EN cc-by Nuclear Fusion 2021-06-02

Abstract Wendelstein 7-X (W7-X), the largest advanced stellarator, is built to demonstrate high power, performance quasi-continuous operation. Therefore, in recent campaign, experiments were performed prepare for long pulse operation, addressing three critical issues: development of stable detachment, control heat and particle exhaust, impact leading edges on plasma performance. The exhaust W7-X realized with help an island divertor, which utilizes large magnetic islands at boundary. This...

10.1088/1741-4326/ac1b68 article EN cc-by Nuclear Fusion 2021-08-06

We show in experiments that a long, underdense, relativistic proton bunch propagating plasma undergoes the oblique instability, which we observe as filamentation. determine threshold value for ratio between transverse size and skin depth instability to occur. At threshold, outcome of experiment alternates filamentation self-modulation (evidenced by longitudinal modulation into microbunches). Time-resolved images density distribution reveal grows an observable level late along bunch,...

10.1103/physreve.109.055203 article EN cc-by Physical review. E 2024-05-07

The magnetic-field perturbation produced by the dynamic ergodic divertor in TEXTOR changes topology of magnetic field plasma edge, creating an open chaotic system. spectrum contains only a few dominant harmonics and therefore it can be described analytical model. modeling is performed vacuum approximation without assuming backreaction does not rely on any experimentally obtained parameters. It shown that this predicts many details observed structure. Several experiments have been to prove...

10.1103/physrevlett.96.035004 article EN Physical Review Letters 2006-01-25
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