Plastic deformation of tungsten under fusion-plasma exposure conditions
Using Nuclear Fusion to produce price-competitive electricity is an important element in the European Research and Development Agenda. The next big step is to create ‘first plasma’ in ITER – the key facility for development of commercial fusion power. While this fusion test-bed is under construction...
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| Tipo de recurso: | tesis doctoral |
| Fecha de publicación: | 2019 |
| País: | España |
| Institución: | Universidad Complutense de Madrid (UCM) |
| Repositorio: | Docta Complutense |
| Idioma: | inglés |
| OAI Identifier: | oai:docta.ucm.es:20.500.14352/16826 |
| Acceso en línea: | https://hdl.handle.net/20.500.14352/16826 |
| Access Level: | acceso abierto |
| Palabra clave: | 539.175.3(043.2) Fusión nuclear Nuclear fusion Física nuclear 2207 Física Atómica y Nuclear |
| Sumario: | Using Nuclear Fusion to produce price-competitive electricity is an important element in the European Research and Development Agenda. The next big step is to create ‘first plasma’ in ITER – the key facility for development of commercial fusion power. While this fusion test-bed is under construction, a number of technical and scientific challenges remain problems that must be solved to enable the efficient and safe operation of ITER. Ensuring proper functioning of the divertor is one of those challenges. The field lines of a diverted plasma deflect particles, in particular impurities, in the scrape-off layer (the region from the vessel region up to the magnetic separatrix, which is the boundary of the confined plasma region) towards the divertor, where they are to be neutralized and removed through a pumping system. The divertor exhausts the heat produced by the fusion reactions and enables the removal of helium and other impurities by apumping system, hence it is a vital component of the whole system... |
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