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Nanostructured tungsten as a first wall material for the future nuclear fusion reactors
Citation
Gordillo Garcia, Nuria 
ORCID: https://orcid.org/0000-0003-2335-738X, Gonzalez Arrabal, Raquel ORCID: https://orcid.org/0000-0002-4955-1925, Rivera de Mena, Antonio ORCID: https://orcid.org/0000-0002-8484-5099, Fernández, I., Briones Fernández-Pola, Fernando, Rio, David del, Gómez, C., Pastor Caño, Jose Ignacio ORCID: https://orcid.org/0000-0003-3561-5999, Tejado Garrido, Elena María ORCID: https://orcid.org/0000-0002-5240-6702, Panizo Laíz, Miguel ORCID: https://orcid.org/0000-0001-9061-7888 and Perlado Martín, José Manuel ORCID: https://orcid.org/0000-0001-6907-4153
(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 |
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| Author/s: |
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| 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 |
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 |
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| DC Identifier: | https://oa.upm.es/19761/ |
| OAI Identifier: | oai:oa.upm.es:19761 |
| Deposited by: | Memoria Investigacion |
| Deposited on: | 15 Feb 2014 11:29 |
| Last Modified: | 30 Oct 2020 15:15 |
