Nanostructured tungsten as a first wall material for the future nuclear fusion reactors

Gordillo Garcia, Nuria and Gonzalez Arrabal, Raquel and Rivera de Mena, Antonio and Fernández, I. and Briones Fernández-Pola, Fernando and Rio, David del and Gómez, C. and Pastor, Jose Ygnacio and Tejado Garrido, Elena María and Panizo Laíz, Miguel and Perlado Martín, José Manuel (2012). Nanostructured tungsten as a first wall material for the future nuclear fusion reactors. In: "Nanostructured tungsten as a first wall material for the future nuclear fusion reactors", 10/09/2012 - 14/09/2012, Madrid, Spain. pp. 1-2.

Description

Title: Nanostructured tungsten as a first wall material for the future nuclear fusion reactors
Author/s:
  • Gordillo Garcia, Nuria
  • Gonzalez Arrabal, Raquel
  • Rivera de Mena, Antonio
  • Fernández, I.
  • Briones Fernández-Pola, Fernando
  • Rio, David del
  • Gómez, C.
  • Pastor, Jose Ygnacio
  • Tejado Garrido, Elena María
  • Panizo Laíz, Miguel
  • Perlado Martín, José Manuel
Item Type: Presentation at Congress or Conference (Speech)
Event Title: Nanostructured tungsten as a first wall material for the future nuclear fusion reactors
Event Dates: 10/09/2012 - 14/09/2012
Event Location: Madrid, Spain
Title of Book: Nanostructured tungsten as a first wall material for the future nuclear fusion reactors
Date: 2012
Subjects:
Faculty: E.T.S.I. Industriales (UPM)
Department: Ingeniería Nuclear [hasta 2014]
Creative Commons Licenses: Recognition - No derivative works - Non commercial

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Abstract

The lack of materials able to withstand the severe radiation conditions (high thermal loads and atomistic damage) expected in fusion reactors is the actual bottle neck for fusion to become a reality. The main requisite for plasma facing materials (PFM) is to have excellent structural stability since severe cracking or mass loss would hamper their protection role which turns out to be unacceptable. Additional practical requirements for plasma facing materials are among others: (i) high thermal shock resistance, (ii) high thermal conductivity (iii) high melting point (iv) low physical and chemical sputtering, and (v) low tritium retention.

More information

Item ID: 19761
DC Identifier: http://oa.upm.es/19761/
OAI Identifier: oai:oa.upm.es:19761
Deposited by: Memoria Investigacion
Deposited on: 15 Feb 2014 11:29
Last Modified: 24 Sep 2018 07:47
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