A5050142622- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Ionosphere and magnetosphere dynamics
- Particle accelerators and beam dynamics
- High-Energy Particle Collisions Research
- Optical measurement and interference techniques
- Advanced Optical Sensing Technologies
- Calibration and Measurement Techniques
- Heat Transfer and Optimization
- Advanced Measurement and Metrology Techniques
- Plasma Diagnostics and Applications
- Optical Coherence Tomography Applications
- nanoparticles nucleation surface interactions
- GNSS positioning and interference
- Fluid Dynamics and Turbulent Flows
- Corrosion Behavior and Inhibition
- Medical Imaging Techniques and Applications
- Induction Heating and Inverter Technology
- Atomic and Subatomic Physics Research
- Model Reduction and Neural Networks
Culham Science Centre
2013-2024
United Kingdom Atomic Energy Authority
2017-2024
Culham Centre for Fusion Energy
2012-2024
Royal Military Academy
2020
PerkinElmer (United States)
2006
Cranfield University
1997-1998
Abstract The JET 2019–2020 scientific and technological programme exploited the results of years concerted engineering work, including ITER-like wall (ILW: Be W divertor) installed in 2010, improved diagnostic capabilities now fully available, a major neutral beam injection upgrade providing record power 2019–2020, tested technical procedural preparation for safe operation with tritium. Research along three complementary axes yielded wealth new results. Firstly, plasma delivered scenarios...
Abstract In 2021 JET exploited its unique capabilities to operate with T and D–T fuel an ITER-like Be/W wall (JET-ILW). This second major campaign (DTE2), after DTE1 in 1997, represented the culmination of a series enhancements—new fusion diagnostics, new injection capabilities, refurbishment plant, increased auxiliary heating, in-vessel calibration 14 MeV neutron yield monitors—as well as significant advances plasma theory modelling community. DTE2 was complemented by sequence isotope...
Abstract The quasi-continuous exhaust (QCE) regime is a that naturally type-I ELM-free. It combines the high density at plasma edge needed for power with normalised energy confinement typical H-mode operation. In QCE large-scale ELMs are avoided and high-frequent, low-amplitude filaments present leading to name-giving transport of particles energy.
This contribution reports first time was successfully achieved in JET metal wall. More so, it demonstrated recent deuterium-tritium...
The 2014–2016 JET results are reviewed in the light of their significance for optimising ITER research plan active and non-active operation. More than 60 h plasma operation with first wall materials successfully took place since its installation 2011. New multi-machine scaling type I-ELM divertor energy flux density to is supported by principle modelling. relevant disruption experiments modelling reported a set three mitigation valves mimicking setup. Insights L–H power threshold Deuterium...
This paper reports the impact on confinement and power load of high-shape 2.5 MA ELMy H-mode scenario at JET a change from all carbon plasma-facing components to an metal wall. In preparation this change, systematic studies reduction as result fuelling in combination with nitrogen seeding were carried out JET-C are compared their counterpart metallic An unexpected significant is reported decrease pedestal but partially recovered injection nitrogen.
Abstract For the past several years, JET scientific programme (Pamela et al 2007 Fusion Eng. Des . 82 590) has been engaged in a multi-campaign effort, including experiments D, H and T, leading up to 2020 first with 50%/50% D–T mixtures since 1997 ever plasmas ITER mix of plasma-facing component materials. this purpose, concerted physics technology was launched view prepare campaign (DTE2). This paper addresses key elements developed by directly contributing preparation. intense preparation...
The original goals of the JET ITER-like wall included study impact an all W divertor on plasma operation (Coenen et al 2013 Nucl. Fusion 53 073043) and fuel retention (Brezinsek 083023). ITER has recently decided to install a full-tungsten (W) from start operations. One key inputs required in support this decision was possibility melting melt splashing during transients. Damage type can lead modifications surface topology which could higher disruption frequency or compromise subsequent...
Views Icon Article contents Figures & tables Video Audio Supplementary Data Peer Review Share Twitter Facebook Reddit LinkedIn Tools Reprints and Permissions Cite Search Site Citation M. N. A. Beurskens, T. H. Osborne, P. Schneider, E. Wolfrum, L. Frassinetti, R. Groebner, Lomas, I. Nunes, S. Saarelma, Scannell, B. Snyder, D. Zarzoso, Balboa, Bray, Brix, J. Flanagan, C. Giroud, Giovannozzi, Kempenaars, Loarte, de la Luna, G. Maddison, F. Maggi, McDonald, Pasqualotto, Saibene, Sartori, Emilia...
This paper reports the progress made at JET-ILW on integrating requirements of reference ITER baseline scenario with normalized confinement factor 1, a pressure 1.8 together partially detached divertor whilst maintaining these conditions over many energy times. The 2.5 MA high triangularity ELMy H-modes are studied two different configurations D-gas injection and nitrogen seeding. power load reduction N seeding is reported. relationship between an increase in pedestal investigated....
The objective of thermonuclear fusion consists producing electricity from the coalescence light nuclei in high temperature plasmas. most promising route to envisages confinement such plasmas with magnetic fields, whose studied configuration is tokamak. Disruptions are catastrophic collapses affecting all tokamak devices and one main potential showstoppers on a commercial reactor. In this work we report how, deploying innovative analysis methods thousands JET experiments covering isotopic...
The inboard limiters for ITER were initially designed on the assumption that parallel heat flux density in scrape-off layer (SOL) could be approximated by a single exponential with decay length λq. This was found not to adequate 2012, when infra-red (IR) thermography measurements inner column during JET limiter discharges clearly revealed presence of narrow channel adjacent last closed surface. near-SOL occurs λq ∼ few mm, much shorter than main SOL λq, and can raise at apex factor up ∼4...
Abstract We present an overview of results from a series L–H transition experiments undertaken at JET since the installation ITER-like-wall (JET-ILW), with beryllium wall tiles and tungsten divertor. Tritium, helium deuterium plasmas have been investigated. Initial in tritium show ohmic transitions low density power threshold for ( P LH ) is lower than ones densities, while we still lack contrasted data to provide scaling high densities. In there notable shift which minimum <?CDATA...
Abstract The recent deuterium–tritium campaign in JET-ILW (DTE2) has provided a unique opportunity to study the isotope dependence of L-H power threshold an ITER-like wall environment (Be and W divertor). Here we present results from dedicated transition experiments at JET-ILW, documenting tritium plasmas, comparing them with matching deuterium hydrogen datasets. From earlier it is known that as plasma isotopic composition changes deuterium, through varying deuterium/hydrogen concentrations,...
Abstract JET returned to deuterium-tritium operations in 2023 (DTE3 campaign), approximately two years after DTE2. DTE3 was designed as an extension of JET's 2022-2023 deuterium campaigns, which focused on developing scenarios for ITER and DEMO, integrating in-depth physics understanding control schemes. These were evaluated with mixed D-T fuel, using the only remaining tritium-capable tokamak until its closure 2023. A core-edge-SOL integrated H-mode scenario developed tested D-T, showing...
Abstract Deuterium (D) and beryllium (Be) fluxes are obtained in JET Low-confinement (L-mode) plasmas at the outer limiters of first wall using calibrated visible cameras. They inferred from measured radiances spectroscopic S/XB method. From fluxes, effective gross erosion yield Yeff limiter surface is estimated. After discussing uncertainties proposed methodology, we show dependence deduced particle recent L-mode on: separatrix-limiter clearance, magnetic field plasma current, NBI ICR...
For the new ITER-like wall at JET, two infrared diagnostics (KL9B, KL3B) have been installed. These can operate between 3.5 and 5 μm up to sampling frequencies of ∼20 kHz. KL9B KL3B image horizontal vertical tiles divertor. The divertor are tungsten coated carbon fiber composite except central tile which is bulk consists lamella segments. thermal emission lamellae affects surface temperature measurement therefore KL9A has upgraded achieve a higher spatial resolution (by factor 2). A...
For the design and operation of large fusion devices a detailed understanding power exhaust processes is necessary.This paper will give an overview current research on divertor load mechanisms.The results shown are obtained in JET with ITER like wall ASDEX Upgrade tungsten coated plasma facing components.The challenges infrared thermography bulk presented.For steady state heat load, fall-off length λ q JET-ILW compared to empirical scaling found carbon components.A first attempt scale...
The new JET ITER-like wall (made of beryllium and tungsten) is more fragile than the former carbon fiber composite requires active protection to prevent excessive heat loads on plasma facing components (PFC). Analog CCD cameras operating in near infrared wavelength are used measure surface temperature PFCs. Region interest (ROI) analysis performed real time maximum measured each ROI sent vessel thermal map. system started October 2011 has already successfully led a safe landing when hot...
Digital twin techniques enhance traditional engineering analysis workflows of existing systems when a realistic evaluation component under complex operating conditions is required. During preparation, commissioning and phases, components can be virtually tested by using validated numerical models, operational expertise, experimental databases. Three complementary applications have been developed this approach. The models used for the divertor tiles are based on continuum mechanics...
The dependence of the H-mode edge transport barrier width on normalized ion gyroradius (ρ * = ρ/a) in discharges with type I ELMs was examined experiments combining data for JET and DIII-D tokamaks.The plasma configuration as well local pressure (β), collisionality (ν ), Mach number ratio electron temperature at pedestal top were kept constant, while ρ varied by a factor four.The steep gradient region (T e ) density (n pedestals
The dynamics and stability of divertor detachment in N 2 seeded, type-I, ELMy H-mode plasmas with dominant NBI heating the JET ITER-like wall device is studied by means an integrated analysis diagnostic data from several systems, classifying relative to ELM times.It thereby possible study response evolution control parameters (SOL input power, upstream density impurity fraction) prevailing during inter-ELM periods effect ELMs on detached divertor.A relatively comprehensive overview achieved,...