A5059743556- Fusion materials and technologies
- Magnetic confinement fusion research
- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Superconducting Materials and Applications
- Nuclear Physics and Applications
- Nuclear materials and radiation effects
- Metallurgical Processes and Thermodynamics
- Ion-surface interactions and analysis
- Diamond and Carbon-based Materials Research
- Metal and Thin Film Mechanics
- High-pressure geophysics and materials
- Heat transfer and supercritical fluids
- High-Energy Particle Collisions Research
- Archaeological Research and Protection
- Anomaly Detection Techniques and Applications
- Advanced materials and composites
- Ionosphere and magnetosphere dynamics
- Metallic Glasses and Amorphous Alloys
- Muon and positron interactions and applications
- High-Temperature Coating Behaviors
- Spacecraft and Cryogenic Technologies
- Fault Detection and Control Systems
- Geological and Geochemical Analysis
Culham Science Centre
2015-2024
United Kingdom Atomic Energy Authority
2001-2024
Culham Centre for Fusion Energy
2013-2023
Royal Military Academy
2020
VTT Technical Research Centre of Finland
2014
Institute of Engineering Physics
2013
Moscow Engineering Physics Institute
2013
University of Sussex
2003-2009
Fusion UK
2003-2008
University of Toronto
2008
Management of tritium inventory remains one the grand challenges in development fusion energy, and choice plasma-facing materials is a key factor for in-vessel retention. The Atomic Molecular Data Unit International Energy Agency organized Coordinated Research Project (CRP) on overall topic reactors during period 2001-2006. This dealt with hydrogenic retention ITER's – Be, C, W compounds (mixed materials) these elements as well removal techniques. results CRP are summarized this paper...
JET is used as a test bed for ITER, to investigate beryllium migration which connects the lifetime of first-wall components under erosion with tokamak safety, in relation long-term fuel retention. The (i) limiter and (ii) divertor configurations have been studied JET-ILW (JET Be first wall W divertor), compared those former JET-C carbon-based plasma-facing (PFCs)). For configuration, gross at contact point was determined situ by spectroscopy between 4% (Ein = 35 eV) more than 100%, caused...
The issue of first wall and divertor target lifetime represents one the greatest challenges facing successful demonstration integrated tokamak burning plasma operation, even in case planned next step device, ITER, which will run at a relatively low duty cycle comparison to future fusion power plants. Material erosion by continuous or transient ion neutral impact, susbsequent transport released impurities through their deposition and/or eventual re-erosion constitute process migration. Its...
In the period 1998—2001 JET tokamak was operated with MkII Gas Box divertor. On two occasions during that a number of limiter and divertor tiles were retrieved from torus then examined ex situ surface sensitive techniques. Erosion deposition patterns determined in order to assess material erosion, migration fuel inventory on plasma facing components. Tracer techniques, e.g. injection 13C labelled methane coated low-Z high-Z marker layer, used enhance volume information transport. The results...
Post mortem analyses of JET ITER-Like-Wall tiles and passive diagnostics have been completed after each the first two campaigns (ILW-1 ILW-2). They show that global fuel inventory is still dominated by co-deposition; hence plasma parameters sputtering processes affecting material migration influence distribution retained fuel. In particular, differences between results from may be attributed to a greater proportion pulses run with strike points in divertor corners, having about 300...
Abstract Results of the first dust survey in JET with ITER-Like Wall (JET-ILW) are presented. The sampling was performed using adhesive stickers from divertor tiles where greatest material deposition detected after JET-ILW campaign 2011 – 2012. emphasis especially on and analysis metal particles (Be W) aim to determine composition, size, surface topography internal structure a large set methods: high-resolution scanning transmission electron microscopy, focused ion beam, diffraction also...
The work presented draws on new analysis of components removed following the second JET ITER-like wall campaign 2013–14 concentrating upper inner divertor, and outer divertor corners, lifetime issues relating to tungsten coatings carbon fibre composite tiles dust/particulate generation. results show that remains region highest deposition in JET-ILW. Variations plasma configurations between first have altered material migration corners divertor. Net is shown be beneficial sense it reduces W...
This paper reports on the first post-mortem analyses of tiles removed from JET after campaigns with ITER-like wall (ILW) during 2011–12 [1]. Tiles divertor have been analysed by ion beam analysis techniques and secondary mass spectrometry to determine amount beryllium deposition deuterium retention in exposed scrape-off layer. Films 10–20 μm thick were present at top tile 1, but only very thin films (< 1 μm) found shadowed areas other tiles. The total Be following ILW campaign was a factor ∼...
Abstract An assessment of the tritium (T) inventory in plasma facing components (PFC) during JET T and deuterium-tritium (DT) operations is presented based on most comprehensive ex situ fuel retention data set PFCs from 2015-2016 ILW3 operating period presented. The global 4.19 × 10 23 D atoms, 0.19% injected fuel. inner divertor remains region highest (46.5%). at end calculated as 7.48 22 atoms informative for accountancy, clean-up efficacy waste liability assessments. accumulation rate...
Post-mortem analyses of individual components provide relevant information on plasma-surface interactions like tungsten erosion, beryllium deposition and plasma fuel retention with divertor tiles via implantation or co-deposition. Ion Beam techniques are ideal tools for such purposes have been extensively used post-mortem selected from JET following each campaign. In this contribution results removed the ITER-Like Wall (JET-ILW) 2013–2014 campaign presented. The summarize along poloidal...
The first divertor was installed in the JET machine between 1992 and 1994 operated with carbon tiles then beryllium 1994–5. Post-mortem studies after these experiments demonstrated that most of impurities deposited originate main chamber, asymmetric deposition patterns generally favouring inner region result from drift scrape-off layer. A new monolithic structure 1996 which produced heavy at shadowed areas corner, is where majority tritium trapped by co-deposition during deuterium-tritium...
This contribution presents two-dimensional Monte-Carlo simulations of the local transport hydrocarbons that are chemically eroded in JET MkIIa divertor. The effect a given background carbon flux flowing from main plasma down to divertor is also taken into account. influence temperatures and densities different assumptions for sticking re-deposited particles hitting tiles analysed. Even under assumption hydrocarbon fragments zero, large amount (about 75%) form ionized on tiles. A reasonable...
Plasma facing components from JET and TEXTOR were studied. The emphasis was on the comparison of co-deposition, material mixing fuel inventory plasma side surfaces tiles, i.e. in gaps separating tiles. Integrated content Mk-I divertor floor approximately two times greater than detected surfaces. Taking into account similarities between structure castellation ITER divertor, impact tile shaping tritium is addressed. Deposition limiter tiles around 3–5% that Experiments aiming at a deeper...
Metallic mirrors will be essential components of all optical spectroscopy and imaging systems for plasma diagnosis that used at the next-step magnetic fusion experiment, International Thermonuclear Experimental Reactor (ITER). Any change mirror performance, in particular, reflectivity, influence quality reliability detected signals. At instigation ITER Design Team, a dedicated technical experimental activity aiming assessment surface degradation as result exposure to has been initiated on...
JET components are removed periodically for surface analysis to assess material migration and fuel retention. This paper describes issues related handling procedures preparing samples analysis; in particular a newly developed procedure cutting beryllium tiles is presented. Consideration also given the hazards likely due increased tritium inventory activation from 14 MeV neutrons following planned TT DT operations (DTE2) 2017. Conclusions drawn as feasibility of post DTE2.