A5088217980- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Nuclear reactor physics and engineering
- Plasma Diagnostics and Applications
- Nuclear Materials and Properties
- Laser-Plasma Interactions and Diagnostics
- Graphite, nuclear technology, radiation studies
- Radiation Dose and Imaging
- Ionosphere and magnetosphere dynamics
- Radiology practices and education
- Mining and Gasification Technologies
- Radioactive Decay and Measurement Techniques
- Metallurgical Processes and Thermodynamics
- Radioactivity and Radon Measurements
- Cold Fusion and Nuclear Reactions
- Particle Accelerators and Free-Electron Lasers
- Pulsed Power Technology Applications
- High-Temperature Coating Behaviors
- Radioactive contamination and transfer
- Iron and Steelmaking Processes
- Advancements in Photolithography Techniques
- Ion-surface interactions and analysis
- Welding Techniques and Residual Stresses
Culham Science Centre
2014-2024
Culham Centre for Fusion Energy
2010-2024
United Kingdom Atomic Energy Authority
2020-2024
Stanford Synchrotron Radiation Lightsource
2022
Scientific Methods (United States)
2022
Forschungszentrum Jülich
2022
Vanderbilt University
2022
Intelligent Fusion Technology (United States)
2022
Society of Nuclear Medicine and Molecular Imaging
2022
Institute of Electrical and Electronics Engineers
2022
For several reasons the challenge to keep loads first wall within engineering limits is substantially higher in DEMO compared ITER. Therefore pre-conceptual design development for that currently ongoing Europe needs be based on load estimates are derived employing most recent plasma edge physics knowledge.
The tritium required for ITER will be supplied from the CANDU production in Ontario, but while Ontario may able to supply 8 kg a DEMO fusion reactor mid-2050s, it not provide 10 at any realistic starting time. start depend on advances plasma fuelling efficiency, burnup fraction, and processing technology. It is theory possible up with little or no tritium, an estimated cost of $2 billion per kilogram saved, economically sensible.
Abstract A sequence of fuel recovery methods was tested in JET, equipped with the ITER-like beryllium main chamber wall and tungsten divertor, to reduce plasma deuterium concentration less than 1% preparation for operation tritium. This also a key activity regard refining clean-up strategy be implemented at end 2nd DT campaign JET (DTE2) assess tools that are envisaged mitigate tritium inventory build-up ITER. The began 4 days baking 320 °C, followed by further which Ion Cyclotron Wall...
The EU DEMO plasma is almost completely enveloped by large breeding blanket segments for tritium and power extraction. Shaping of the plasma-facing wall in 3D may prove to be essential, but this strategy alone not sufficient protect against anticipated transient events. high heat flux wall-limiter approach used ITER thought viable a self-sufficient reactor, so protection using discrete limiters pursued. Two types limiter are described paper. One an equatorial port designed handle during...
The Combined Heating and Magnetic Research Apparatus (CHIMERA) fusion technology test facility is under construction. will be uniquely capable of semi-integral testing materials component modules up to the size ITER blanket module box, combined conditions in-vacuum high heat flux, static pulsed magnetic fields, high-temperature/high-pressure water cooling. This paper reports high-level capabilities CHIMERA baselined design planned program describes proposed strategy for use simulations...
Tritium production is of critical importance to prospective DT fusion power plants. Lithium ceramic and beryllium based solid-type breeder blankets are an option for supplying the tritium required sustain plasma. This research investigates time-varying in solid with different compositions. The fraction was varied conjunction Li 6 enrichment. parameter study considered 198 blanket compositions three thicknesses. cheapest configuration capable meeting requirements were found. cost 4 SiO...
As power plant design programmes approach the transition between pre-conceptual and conceptual phases, systems code PROCESS has been improved to incorporate more detailed plasma physics, engineering, analysis modules. Unlike many codes, combines physics modelling with both technology costs analysis. Some of key topics in phase are toroidal field (TF) magnet design, divertor handling, operational sensitivity, economic uncertainty Models covering these areas have integrated or PROCESS. During...
Abstract The tungsten erosion within Spherical Tokamak for Energy Production (STEP) assuming main wall and divertor has been estimated with ERO at the inner outer divertor, midplane outboard baffle entrance. Plasma parameters are based on SOLPS simulations applying argon puffing edge cooling. plasma parameter range covers peak electron temperatures T e between 3 25 eV in divertor. At ∼ 13 eV, ∼7 entrance 1 4 eV. modelled gross is highest up to 1E19 W m −2 s −1 7E19 one studied. about 2E18...
Although the ultimate goal of most current fusion research is to build an economically attractive power plant, present status physics and technology does not provide performance necessary achieve this goal. Therefore, in order model how such plants may operate what their output might be, extrapolations must be made from existing experimental data technology. However, expected a plant built operating point specifications can only ever 'best guess'. Extrapolations far beyond regimes are...
The design of plasma facing components (PFCs) requires knowledge the charged particle heat load in scrape-off layer (SOL). Ray-tracing codes like PFCFlux can model this assuming that particles follow magnetic field lines. Calculations on limiter equilibria underestimate significantly. In fact, not all power circulating SOL is reported wall, with 80% total missing worst cases. This paper explains why some case, and presents different ways to rescale recover coming from SOL. maximum for a...
Meeting the challenge of realizing fusion power production will require considerable and increasing investment in facilities for testing development technology. Particularly important be components destined harsh in-vessel environment reactor. To help address this need, U.K. Government is investing major new technology facilities, which offer integrated laboratories covering complete life cycle from materials to manufacturing processes load components. A part these shall a test device named...