The Tritium Extraction eXperiment (TEX): A forced convection fusion blanket PbLi loop

A forced convection PbLi loop has been designed and constructed to test tritium extraction from molten PbLi. This Tritium Extraction eXperiment (TEX) is designed to operate at temperatures and tritium concentrations relevant to the helium cooled lead lithium, water cooled lead lithium, and dual cool...

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Bibliographic Details
Published in:Fusion engineering and design 2023-07, Vol.192 (C), p.113737, Article 113737
Main Authors: Taylor, Chase N., Fuerst, Thomas F., Pawelko, Robert J., Shimada, Masashi
Format: Article
Language:English
Subjects:
Blanket
Extraction
PbLi
Tritium
Vacuum permeator
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Summary:A forced convection PbLi loop has been designed and constructed to test tritium extraction from molten PbLi. This Tritium Extraction eXperiment (TEX) is designed to operate at temperatures and tritium concentrations relevant to the helium cooled lead lithium, water cooled lead lithium, and dual coolant lead lithium breeding blankets. The major systems consist of a moving magnet pump, source permeator, supply tank, test section, and plenum. Additional subsystems, including flowmeters, pressure gauges, valves, and heaters are described. The versatile design of TEX will enable code validation using simple tubular membranes, as well as determining tritium extraction efficiencies for alternative test sections.
ISSN:0920-3796
1873-7196
DOI:10.1016/j.fusengdes.2023.113737