Tritium permeation experiment at IFMIF Medium Flux Test Module

Casal Iglesias, Natalia; García, A.; Ibarra, A.; Sordo, Fernando; Rapisarda, D.; Queral, V. y Mota, F. (2009). Tritium permeation experiment at IFMIF Medium Flux Test Module. "Fusion Engineering and Design", v. 84 (n. 2-6); pp. 559-564. ISSN 0920-3796. https://doi.org/10.1016/j.fusengdes.2008.12.106.

Descripción

Título: Tritium permeation experiment at IFMIF Medium Flux Test Module
Autor/es:
  • Casal Iglesias, Natalia
  • García, A.
  • Ibarra, A.
  • Sordo, Fernando
  • Rapisarda, D.
  • Queral, V.
  • Mota, F.
Tipo de Documento: Artículo
Título de Revista/Publicación: Fusion Engineering and Design
Fecha: Junio 2009
Volumen: 84
Materias:
Palabras Clave Informales: IFMIF; DEMO; Liquid breeders; Tritium permeation
Escuela: E.T.S.I. Industriales (UPM)
Departamento: Otro
Licencias Creative Commons: Reconocimiento - Sin obra derivada - No comercial

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Resumen

Tritium release experiments using different breeding material candidates are planned for the medium flux region of the IFMIF Test Cell. Nowadays, only ceramic breeder materials have been suggested to be tested in the Tritium Release Module located in the Medium Flux Test Module of IFMIF. Liquid breeder blankets are very promising and for that reason, several concepts will be tested in ITER. One of the main problems concerning the liquid blankets is the permeation of the generated tritium in the breeder throughout the walls. Since tritium permeation is highly influenced by irradiation conditions, IFMIF is a suitable scenario to perform tritium permeation related experiments. In this paper, a preliminary design of a tritium permeation experiment for the Medium Flux Test Module of IFMIF is proposed, in order to contribute to the progress of the liquid breeder blanket concept validation. The conceptual design of the capsule in which the experiment will be performed is carried out, taking into consideration the experiment necessities and its implementation in the Tritium Release Module. In addition to this, some thermal hydraulic calculations have been performed to evaluate the thermal behaviour of the irradiation capsule

Más información

ID de Registro: 38715
Identificador DC: http://oa.upm.es/38715/
Identificador OAI: oai:oa.upm.es:38715
Identificador DOI: 10.1016/j.fusengdes.2008.12.106
URL Oficial: http://www.sciencedirect.com/science/journal/09203796
Depositado por: Memoria Investigacion
Depositado el: 14 Dic 2015 16:45
Ultima Modificación: 16 Dic 2015 15:07
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