A5109040115- Fusion materials and technologies
- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Particle accelerators and beam dynamics
- Spacecraft and Cryogenic Technologies
- Laser-Plasma Interactions and Diagnostics
- Nuclear Physics and Applications
- Metallurgical Processes and Thermodynamics
- Rocket and propulsion systems research
- Advanced Thermodynamic Systems and Engines
- Particle Accelerators and Free-Electron Lasers
- Advanced ceramic materials synthesis
- Muon and positron interactions and applications
- Catalytic Processes in Materials Science
- Structural Integrity and Reliability Analysis
- Modeling, Simulation, and Optimization
- Solar-Powered Water Purification Methods
- Electromagnetic Launch and Propulsion Technology
- Radiation Effects in Electronics
- School Choice and Performance
- Powder Metallurgy Techniques and Materials
- Thermodynamic and Structural Properties of Metals and Alloys
- Nuclear Engineering Thermal-Hydraulics
Culham Science Centre
2016-2024
Culham Centre for Fusion Energy
2021-2024
University of Edinburgh
2023
United Kingdom Atomic Energy Authority
2022
European Commission
2021-2022
Max Planck Institute for Plasma Physics
2002-2016
Max Planck Society
2008-2015
London School of Economics and Political Science
2014
Österreichischer Rundfunk
2014
University of Buckingham
2014
The next step in the Wendelstein stellarator line is large superconducting device 7-X, currently under construction Greifswald, Germany. Steady-state operation an intrinsic feature of stellarators, and one key element 7-X mission to demonstrate steady-state plasma conditions relevant for a fusion power plant. device, on hand, requires implementation special technologies, giving rise technical challenges during design, fabrication assembly such device. On other also physics development at...
Abstract A series of experiments have been executed at JET to assess the efficacy newly installed shattered pellet injection (SPI) system in mitigating effects disruptions. Issues, important for ITER disruption mitigation system, such as thermal load mitigation, avoidance runaway electron (RE) formation, radiation asymmetries during quench electromagnetic control and RE energy dissipation addressed over a large parameter range. The efficiency has examined various SPI strategies. paper...
Abstract Runaway electrons (REs) created during tokamak disruptions pose a threat to the reliable operation of future larger machines. Experiments using shattered pellet injection (SPI) have been carried out at JET investigate ways prevent their generation or suppress them if avoidance is not sufficient. Avoidance possible SPI contains sufficiently low fraction high-Z material, it fired early in advance disruption prone runaway generation. These results are consistent with previous similar...
In view of the planned DT operations at JET, a calibration JET neutron monitors 14 MeV energy is needed using generator deployed inside vacuum vessel by remote handling system. The target accuracy this ±10% as also required ITER, where precise yield measurement important, e.g. for tritium accountancy. To achieve accuracy, selected source has been fully characterised and calibrated prior to in-vessel monitors. This paper describes measurements performed different types detectors,...
A new DT campaign (DTE2) is planned at JET in 2020 to minimize the risks of ITER operations. In view operations, a calibration neutron monitors 14 MeV energy has been performed using well calibrated generator (NG) deployed, together with its power supply and control unit, inside vacuum vessel by remote handling system. The NG was equipped two diamond detectors, which continuously monitored emission rate during calibration, activation foils provided time integrated yield. Cables embedded boom...
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 objective of Wendelstein 7-X is to demonstrate steady-state operation at β -values up 5%, ion temperatures several keV and plasma densities 2 × 1020 m−3. second operational phase foresees a fully high heat flux (HHF) divertor. Preparations are underway cope with residual bootstrap currents, either by electron cyclotron current drive or HHF protection elements. main heating system an resonance facility. Various technical improvements the gyrotrons have been implemented recently. They...
The actively water-cooled plasma facing components (PFCs) of the Wendelstein 7-X stellarator consisting first wall protection and divertor systems have a total surface area about 265m2. complex 3D geometry vessel with 244 ports dedicated to diagnostics, heating water-cooling pipe-work together need minimize space taken significant heat loads expected on presents design manufacturing challenges.The divertor, made 100 target modules, has an 19 m2. Each module is formed from elements CFC flat...
The use of carbon-based materials, i.e. graphite and carbon fibre composites (CFCs), as plasma facing materials in experimental nuclear fusion devices is widely spread. For the strike point area ITER divertor, a European candidate material was NB31, three directional (3D) CFC consisting ex-pitch, ex-PAN needled fibres, which will be replaced future by newly developed NB41. This composite used for fabrication divertor components Wendelstein 7-X. In frame an extensive characterization on...