Tritium control modelling for a helium cooled lithium–lead blanket of a fusion power reactor-Reference-Cited by-同舟云学术

Tritium control modelling for a helium cooled lithium–lead blanket of a fusion power reactor

Published:2006-02 Issue:1-7 Volume:81 Page:753-762
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Farabolini W.,Ciampichetti A.,Dabbene F.,Fütterer M.A.,Giancarli L.,Laffont G.,Puma A. Li,Raboin S.,Poitevin Y.,Ricapito I.,Sardain P.

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference15 articles.

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2. P. Lo Pinto, Safety analysis of helium-cooled lithium–lead test blanket module for ITER, CEA/DEN/CAD/DER/SESI/LESA/NT DO4, 2004, p. 15.

3. M.A. Fütterer, Tritium control for lithium–lead fusion blankets, Ph.D. thesis, Institut National Polytechnique de Toulouse, France, 1993, p. 30.

4. Solubility and diffusivity of hydrogen isotopes in liquid Pb–17Li;Reiter;Fusion Eng. Des.,1991

5. A. Aiello, A. Ciampichetti, G. Benamati, Hydrogen permeability and embrittlement in Eurofer 97 martensitic steel, ENEA Report SM-A-R-001, 2003.

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