A5089009976- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Ionosphere and magnetosphere dynamics
- Particle accelerators and beam dynamics
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Nuclear Materials and Properties
- Nuclear Physics and Applications
- Meteorological Phenomena and Simulations
- Physics of Superconductivity and Magnetism
- High-Energy Particle Collisions Research
- Solar and Space Plasma Dynamics
- Dust and Plasma Wave Phenomena
- Non-Destructive Testing Techniques
- Atomic and Molecular Physics
- Metal and Thin Film Mechanics
- Plasma and Flow Control in Aerodynamics
- Nuclear Engineering Thermal-Hydraulics
- Advancements in Semiconductor Devices and Circuit Design
- Magnetic Properties and Applications
- Muon and positron interactions and applications
- Fluid Dynamics and Turbulent Flows
- Magnetic Field Sensors Techniques
ITER
2015-2024
Culham Science Centre
2003-2021
Culham Centre for Fusion Energy
2004-2021
Princeton Plasma Physics Laboratory
2021
Princeton University
2021
Plasma Technology (United States)
2021
Fusion Academy
2015-2021
Fusion (United States)
2015-2021
General Atomics (United States)
2020
Donghua University
2020
Progress, since the ITER Physics Basis publication (ITER Editors et al 1999 Nucl. Fusion 39 2137–2664), in understanding processes that will determine properties of plasma edge and its interaction with material elements is described. Experimental areas where significant progress has taken place are energy transport scrape-off layer (SOL) particular anomalous scaling, particle SOL plays a major role diverted plasmas main-chamber elements, localized mode (ELM) deposition on mechanism for ELM...
The 'Progress in the ITER Physics Basis' (PIPB) document is an update of 'ITER (IPB), which was published 1999 [1]. IPB provided methodologies for projecting performance burning plasmas, developed largely through coordinated experimental, modelling and theoretical activities carried out on today's large tokamaks (ITER R&D). In IPB, projections (1998 Design) were also presented. pointed some outstanding issues. These issues have been addressed by Participant Teams (the European Union, Japan,...
Analysis of Type I ELMs from ongoing experiments shows that ELM energy losses are correlated with the density and temperature pedestal plasma before crash. The loss normalized to is found correlate across collisionality (ν*ped), decreasing increasing ν*ped. Other parameters affect size, such as edge magnetic shear, etc, which influence volume affected by ELMs. particle influenced this weakly dependent on other parameters. In JET DIII-D, under some conditions, can be observed (`minimum'...
Interactions between the plasma and vessel walls constitute a major engineering problem for next step fusion devices, such as ITER, determining choice of plasma-facing materials. A prominent issue in this is tritium inventory build-up vessel, which must be limited safety reasons. The initial material selection, i.e. beryllium (Be) on main walls, tungsten (W) divertor upper baffle dome, carbon fibre composite around strike points plates, results both from attempt to reduce optimize lifetime...
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...
This paper presents the results of a preliminary assessment conducted to estimate thermal response and erosion lifetime ITER divertor targets clad either with carbon-fibre composite or tungsten during type I ELMs. The one-dimensional thermal/erosion model, used for analyses, is briefly described. It includes all key surface heat transfer processes such as evaporation, melting, radiation, their interaction bulk response, it based on an implicit finite-difference scheme, which allows...
The experimental characteristics of divertor detachment in the JET tokamak with Mark I pumped are presented for ohmic, L mode and ELMy H experiments main emphasis on discharges deuterium fuelling only. range over which is observed various regimes, as well influence configuration, direction toroidal field, target material active pumping detachment, will be described. characteristics, such existence a considerable electron pressure drop along field lines scrape-off layer (SOL), compatibility...
As part of the ITER Design Review and in response to issues identified by Science Technology Advisory Committee, physics requirements were reviewed as appropriate updated. The focus this paper will be on recent work affecting design with special emphasis topics near-term procurement arrangements. This describe results on: sensitivity studies, poloidal field coil requirements, vertical stability, effect toroidal ripple thermal confinement, material choice heat load for plasma-facing...
The ITER divertor design is the culmination of years physics and engineering effort, building confidence that this critical component will satisfy requirements meet challenge burning plasma operation. With 54 cassette assemblies, each weighing ∼9 tonnes, nearly 3900 actively cooled high heat flux elements rated to steady-state surface power densities 10 MW m−2 a total ∼60 000 carbon fibre composite monoblocks ∼260 tungsten monoblocks/flat tiles, be largest most advanced its kind ever...
Recent research in scrape-off layer (SOL) and divertor physics is reviewed; new existing data from a variety of experiments have been used to make cross-experiment comparisons with implications for further ITER. Studies the region near separatrix addressed relationship profiles turbulence as well scaling parallel power flow. Enhanced low-field side radial transport implicated driving flows inboard side. The medium-n nature edge localized modes (ELMs) has elucidated measurements determined...
The XGC1 edge gyrokinetic code is used for a high fidelity prediction the width of heat-flux to divertor plates in attached plasma condition. simulation results are validated against empirical scaling $\lambda_q \propto B_P^{-\gamma}$ obtained from present tokamak devices, where $\lambda_q$ mapped outboard midplane and $\gamma_q=1.19$ as defined by T. Eich et al. [Nucl. Fusion 53 (2013) 093031], $B_P$ magnitude poloidal magnetic field at separatrix surface. This predicts \leq 1mm$ when...
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...
Operation of DEMO in comparison to ITER will be significantly more demanding, as various additional limitations physical and technical nature have respected. In particular a set extremely restrictive boundary conditions on divertor operation during between ELMs It is high importance describe these order consider them early possible the ongoing development concept design. This paper extrapolates existing physics basis power particle exhaust DEMO.
Abstract The tritium aspects of the DT fuel cycle embody some most challenging feasibility and attractiveness issues in development fusion systems. review analyses this paper provide important information to understand quantify these challenges define phase space plasma physics technology parameters features that must guide a serious R&D world program. We focus particular on components, necessary satisfy three ‘principal requirements’: (1) achieving self-sufficiency within system, (2)...
DIII-D experiments on rapid shutdown runaway electron (RE) beams have improved the understanding of processes involved in RE beam control and dissipation. Improvements feedback enabled stable confinement out to volt-second limit ohmic coil, as well enabling a ramp down zero current. Spectroscopic studies shown that neutrals tend be excluded from centre. Measurements energy distribution function indicate broad with mean order several MeV peak energies 30–40 MeV. The appears more skewed...
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...