Título:
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Assessment of retention of plasma components in tungsten under high flux plasma exposure:multiscale modeling approach
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Autores:
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Grigorev, Petr
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Tipo de documento:
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texto impreso
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Editorial:
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Universidad Complutense de Madrid, 2017-04-27
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Dimensiones:
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application/pdf
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Nota general:
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info:eu-repo/semantics/openAccess
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Idiomas:
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Palabras clave:
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Estado = No publicado
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Materia = Ciencias: Física: Física nuclear
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Tipo = Tesis
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Resumen:
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Nuclear fusion can be regarded as a potentially clean, secure and virtually unlimited source of energy for the future. Currently, the most promising reactor concept – the so-called "tokamak" device employs magnetic confinement of fusion plasma. One of the most ambitious energy-related projects today is the construction of the world’s largest tokamak, also known as ITER, “The Way” in Latin. The experimental campaigns planned at ITER aim at testing integrated technologies, materials and physical regimes necessary for commercial production of fusion-based electricity. In other words, ITER aims at bridging the gap between today’s smaller fusion devices and the demonstrational power plant of the future, the DEMO reactor...
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En línea:
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https://eprints.ucm.es/id/eprint/56656/1/T41194.pdf
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