Tritium permeation experiment at IFMIF Medium Flux Test Module

Casal Iglesias, Natalia and García, A. and Ibarra, A. and Sordo, Fernando and Rapisarda, D. and Queral, V. and 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.

Description

Title: Tritium permeation experiment at IFMIF Medium Flux Test Module
Author/s:
  • Casal Iglesias, Natalia
  • García, A.
  • Ibarra, A.
  • Sordo, Fernando
  • Rapisarda, D.
  • Queral, V.
  • Mota, F.
Item Type: Article
Título de Revista/Publicación: Fusion Engineering and Design
Date: June 2009
ISSN: 0920-3796
Volume: 84
Subjects:
Freetext Keywords: IFMIF; DEMO; Liquid breeders; Tritium permeation
Faculty: E.T.S.I. Industriales (UPM)
Department: Otro
Creative Commons Licenses: Recognition - No derivative works - Non commercial

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Abstract

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

More information

Item ID: 38715
DC Identifier: http://oa.upm.es/38715/
OAI Identifier: oai:oa.upm.es:38715
DOI: 10.1016/j.fusengdes.2008.12.106
Official URL: http://www.sciencedirect.com/science/journal/09203796
Deposited by: Memoria Investigacion
Deposited on: 14 Dec 2015 16:45
Last Modified: 16 Dec 2015 15:07
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