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Author Gentile, C.A. ♦ Zakharov, L.E. ♦ Woolley, R.D. ♦ Huber, C.J.
Source IEEE Xplore Digital Library
Content type Text
Publisher Institute of Electrical and Electronics Engineers, Inc. (IEEE)
File Format PDF
Copyright Year ©2013
Language English
Subject Domain (in DDC) Technology ♦ Engineering & allied operations
Subject Keyword Lithium ♦ Surface treatment ♦ Inductors ♦ Fuels ♦ Magnetic liquids ♦ Plasma temperature ♦ Fusion reactors ♦ tritium ♦ lithium
Abstract A concern for fusion energy production reactors is tritium inventory resident in vacuum vessel enclosures during and after D-T operations. An immediate issue is the radiological safety associated with large quantities of tritium at risk. Additionally, there is an economic concern associated with the cost of tritium, having a current value in excess of $30 K/gram. Lithium has safely been deployed in fusion research reactors with good success. Our concept builds upon existing work, exploiting the ability of lithium to flow in toroidal and poloidal directions. In our deployment configuration, Li is used to bind with tritium deposited on main surfaces within the reactor vacuum vessel and ancillary internal components. Lithium can be used to wet appropriate surfaces within the vacuum vessel for the purpose of removing surface tritium from internal reactor structures, thus making it available for reuse as fuel.
Description Author affiliation: Princeton Plasma Phys. Lab., Princeton, NJ, USA (Gentile, C.A.; Zakharov, L.E.; Woolley, R.D.; Huber, C.J.)
Educational Role Student ♦ Teacher
Age Range above 22 year
Educational Use Research ♦ Reading
Education Level UG and PG
Learning Resource Type Article
Publisher Date 2013-06-10
Publisher Place USA
Rights Holder Institute of Electrical and Electronics Engineers, Inc. (IEEE)
e-ISBN 9781479901715
Size (in Bytes) 329.67 kB
Page Count 2
Starting Page 1
Ending Page 2

Source: IEEE Xplore Digital Library