A5036649219- Magnetic confinement fusion research
- Fusion materials and technologies
- Laser-Plasma Interactions and Diagnostics
- Superconducting Materials and Applications
- Plasma Diagnostics and Applications
- Nuclear Physics and Applications
- Laser-induced spectroscopy and plasma
- Particle accelerators and beam dynamics
- Nuclear reactor physics and engineering
- Ionosphere and magnetosphere dynamics
- Atomic and Molecular Physics
- Cold Fusion and Nuclear Reactions
- Ion-surface interactions and analysis
- Atomic and Subatomic Physics Research
- Diamond and Carbon-based Materials Research
- Vacuum and Plasma Arcs
- Laser Design and Applications
- Nuclear Engineering Thermal-Hydraulics
- Nuclear Materials and Properties
- Nuclear and radioactivity studies
- High-pressure geophysics and materials
- Electrostatic Discharge in Electronics
- High voltage insulation and dielectric phenomena
- Quantum, superfluid, helium dynamics
- Plasma Applications and Diagnostics
Institute of Plasma Physics and Laser Microfusion
2016-2025
Culham Science Centre
2016-2024
Culham Centre for Fusion Energy
2019-2024
Plasma Technology (United States)
2021
Royal Military Academy
2020
Palo Alto Veterans Institute for Research
2015
Ghent University
2014
University of Lisbon
2012
Czech Technical University in Prague
2008
Electron and ion beam dynamics of the PF-1000 facility were investigated for first time at its upper energy limit (≈1 MJ) in relation to neutron emission, pinch's plasma ('target') characteristics some other parameters with help a number diagnostics ns temporal resolution. Special attention was paid spatial cross correlations different phenomena. Results these experiments are favour emission model based on beam–plasma interaction three important features: (1) target is hot confined during...
With WEST (Tungsten Environment in Steady State Tokamak) (Bucalossi et al 2014 Fusion Eng. Des. 89 907–12), the Tore Supra facility and team expertise (Dumont Plasma Phys. Control. 56 075020) is used to pave way towards ITER divertor procurement operation. It consists implementing a configuration installing ITER-like actively cooled tungsten monoblocks tokamak, taking full benefit of its unique long-pulse capability. user platform, open all partners. This paper describes physics basis WEST:...
Abstract In JET deuterium-tritium (D-T) plasmas, the fusion power is produced through thermonuclear reactions and between thermal ions fast particles generated by neutral beam injection (NBI) heating or accelerated electromagnetic wave in ion cyclotron range of frequencies (ICRFs). To complement experiments with 50/50 D/T mixtures maximizing reactivity, a scenario dominant non-thermal reactivity has been developed successfully demonstrated during second campaign DTE2, as it was predicted to...
Abstract The JET hybrid scenario has been developed from low plasma current carbon wall discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with ITER-like Be/W wall. development started pure Deuterium refinement of current, and toroidal magnetic field choices succeeded solving heat load challenges arising 37 MW injected power ITER like environment, keeping radiation edge core controlled, avoiding MHD instabilities reaching high neutron rates. have re-run Tritium...
A selection of achievements and first physics results are presented the European Integrated Tokamak Modelling Task Force (EFDA ITM-TF) simulation framework, which aims to provide a standardized platform an integrated modelling suite validated numerical codes for prediction complete plasma discharge arbitrary tokamak.The framework developed by ITM-TF, based on generic data structure including both simulated experimental data, allows development sophisticated simulations (workflows)...
This paper (paper I) presents the first part of results obtained with PF-1000 facility for time at its upper energy limit (≈1 MJ). Special attention is paid here to plasma ('pinch') dynamics, which was investigated in relation electro-technical and radiation (especially neutron) characteristics help a number diagnostics, both time-integrated nanosecond temporal resolution. In these methods we utilized Rogowski coil routine measurements, visual multi-frame streak cameras, soft x-ray pin-hole...
Scenario modelling for the demonstration fusion reactor (DEMO) has been carried out using a variety of simulation codes.Two DEMO concepts have analysed: pulsed tokamak, characterised by rather conventional physics and technology assumptions (DEMO1) steady-state with moderately advanced (DEMO2).Sensitivity to impurity concentrations, radiation, heat transport models investigated.For DEMO2, impact current driven non-inductively Neutral Beams studied full MonteCarlo simulations fast ion...
In the present work, role of plasma facing components protection in driving EU-DEMO design will be reviewed, focusing on steady-state and, especially, transients. This work encompasses both first wall (FW) as well divertor. fact, while ITER divertor heat removal technology has been adopted, FW concept shown past years to inadequate for EU-DEMO. is due higher foreseen irradiation damage level, which requires structural materials (like Eurofer) able withstand more than 5 dpa neutron damage....
The reduction in divertor target power load due to radiation of sputtered and externally seeded impurities tokamak fusion reactors is investigated. approach based on integrated numerical modelling DEMO discharges using the COREDIV code, which self-consistently solves 1D radial transport equations plasma core region 2D multifluid SOL. Calculations are performed for inductive scenarios steady-state configurations with tungsten walls Ar or Ne seeding. For all considered significant can be...
The "European Transport Simulator" (ETS) [1,2] is the new modular package for 1-D discharge evolution developed within EFDA Integrated Tokamak Modelling (ITM) Task Force.It consists of precompiled physics modules combined into a workflow through standardized input/output data-structures.Ultimately, ETS will allow an entire simulation from start up until current termination phase, including controllers and sub-systems.The paper presents status towards this ultimate goal.It discusses design...
Abstract The experimental and theoretical analysis were focused on experiments conducted to assess the effect of plasma isotopes, protium (H), deuterium (D), tritium (T) ion cyclotron resonance heating (ICRH) related wall interactions. Comparison L-mode discharges with N = 1 3 He H minority ICRH scenarios done for different isotopes. For selected pulses, behaviour high-Z, mid-Z low-Z intrinsic impurity radiated power was investigated based data from VUV, visible spectroscopy, bolometry...
The laser interferometry and X-ray diagnostic studies were performed within the PF-1000 facility operated with maximum current of 2 MA deuterium gas filling (ensuring neutron yield above ). At this current, plasmoidal, helical toroidal structures formed inside plasma column. Some them penetrated column surface later on dissolved dense period their life was from a few tens to hundreds nanoseconds density higher than in neighbor regions. It could be explained as result pinching by magnetic...
A plasma column generated in the PF-1000 device working deuterium gas at a current level of 1 MA was investigated with interferometric diagnostics and scintillation detectors. The beam diagnostic laser 527-nm wavelength optically split into 16 beams time delay range from 0 to 220 ns. This tool makes possible imaging evolution pinch geometry, axial radial distributions density stagnation phase, their comparison X-ray neutron production. dense structure is described respect its importance for...
A PF-1000 device working with a deuterium gas filling and current on the order of 1 MA was used for studies pinch-column structure by means laser interferometric system at period hard X-ray (HXR) neutron production. Three different phases plasma-column evolution, corresponding to intense HXR emission, were studied discharges yields equal about 10 <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">11</sup> neutrons/shot. First, start stagnation...
Plasma focus experiments were carried out at a modified PF-1000 where the cathode disc was added in front of anode. Experimental results indicated fraction thermonuclear neutrons on mega-ampere current level. In order to prove mechanism, time neutron production and energy spectrum measured by time-of-flight (TOF) diagnostics. Neutron TOF signals showed that multiphase process more than one mechanism occurred simultaneously. The occurrence most evident during plasma stagnation low deuterium...
The PF-1000 plasma focus was modified by adding the cathode disk 3 cm in front of anode. This modification facilitated evaluation neutron energy spectra. Two pulses were distinguishable. As regards first pulse, it lasted 40 ns during stagnation and demonstrated high isotropy emission. A peak detected upstream 2.46±0.02 MeV. full width spectra 90±20 keV enabled to calculate an ion temperature 1.2 keV. These parameters a yield 109 corresponded theoretical predictions for thermonuclear neutrons.
Fast neutrons from deuteron-deuteron fusion reactions were used for a study of fast deuterons in the PF-1000 plasma-focus device. The energy spectrum was determined by time-of-flight method using ten scintillation detectors positioned downstream, upstream, and side-on experimental facility. Neutron energy-distribution functions enabled determination axial radial components producing neutrons, as well rough evaluation total distribution all pinch. It found that deuteron function decreases...
This paper analyzes a possible operational space for the DEMO device with tin divertor. The simulation is performed COREDIV code which self-consistently solves core and scrape-off layer transport equations plasma impurity. A simple model of divertor surface evaporation was included in code. 1 April 2015 configuration. Influence sputtering, prompt redeposition liquid taken into account. Simulation without impurity seeding shown that characterized higher than 80% radiation fraction, 55 MW...
Abstract The two best performing pulses of the so called ITER-Baseline scenario ( I p = 3.5 MA and P in ≈ 35 MW) JET-ITER like wall, one deuterium (D) other deuterium–tritium (D–T) plasma are examined compared this study. Generally, D–T Baseline exhibit an electron density level higher than D energy is comparable by up to 20%, reaching about 12 MJ pulse studied here. In contrast with pulses, often characterised increase time radiated power mantle region (0.70 < ρ 0.95), which may lead...
A key mission for the next-step fusion tokamak device China Fusion Engineering Test Reactor (CFETR) is demonstrating tritium self-sufficiency, which requires a sufficiently high burnup fraction (fburnup) in order to match practically achievable breeding ratio (TBR) with blanket design constraints. Core-edge coupling simulations are performed investigate dependence of fburnup on different controlling parameters CFETR scenarios. Core plasma profiles range pedestal densities simulated by...