Tritium and Impurity Removal from a Liquid Pb-Li Blanket
36th Annual CNS-CNA Student Conference - 2012 June 12


Presented at:
36th Annual CNS-CNA Student Conference
2012 June 12
Location:
Saskatoon, Canada
Session Title:
CNS/CNA Student Conference 2012

Authors:
Rabi Yari (UOIT )
Peter Schwanke (UOIT )
Matthew Kaye (UOIT )
  

Abstract

Tritium and radioactive impurities result in fusion reactors having a Pb-Li liquid blanket via interactions of neutrons with the lithium and lead. The tritium and impurities are to be extracted for use as fuel and to maintain blanket performance as well as provide a safe operating environment. The proposed design for tritium removal consists of a vacuum permeation method whereby niobium is used as the principle permeating window. A laser isotope separation method is also proposed for removal of the impurities. The tritium concentrations, partial pressures, and removal rates have been investigated as part of the design of the removal system and the results are presented.

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