Abstract
In the framework of the European Programme on Fusion Reactor Technology, one of the options chosen for extracting the energy produced is to place a tritium breeding blanket of modules containing the eutectic Li17Pb83 around the plasma.
This is a preview of subscription content, log in via an institution.
Buying options
Tax calculation will be finalised at checkout
Purchases are for personal use only
Learn about institutional subscriptionsPreview
Unable to display preview. Download preview PDF.
Author information
Authors and Affiliations
Editor information
Editors and Affiliations
Rights and permissions
Copyright information
© 1995 Springer Science+Business Media New York
About this chapter
Cite this chapter
Desreumaux, J., Latgé, C., Le Texier, J., Poinsot, S. (1995). Development of a New Plugging Indicator and Experimental Tests in a Lithium Lead Facility. In: Borgstedt, H.U., Frees, G. (eds) Liquid Metal Systems. Springer, Boston, MA. https://doi.org/10.1007/978-1-4615-1977-5_23
Download citation
DOI: https://doi.org/10.1007/978-1-4615-1977-5_23
Publisher Name: Springer, Boston, MA
Print ISBN: 978-1-4613-5814-5
Online ISBN: 978-1-4615-1977-5
eBook Packages: Springer Book Archive