Abstract
Future fusion reactors must be able to breed the tritium they will consume. Several breeding and tritium extraction technologies are under investigation internationally. PbLi is of particular interest as a breeder material. A new forced convection PbLi loop, the Tritium Extraction eXperiment (TEX), is being designed and constructed to investigate tritium extraction from PbLi. Specifically, TEX will serve to investigate the extraction efficiency of various vacuum permeator membranes and configurations. The major components of the loop include a moving magnet pump, reverse permeator, furnace test section, analysis chamber, supply tank, and plenum. As significant hazards are present in such experiments, safety is an integral focus of the experimental design.
| Original language | English |
|---|---|
| Pages (from-to) | 829-835 |
| Number of pages | 7 |
| Journal | Fusion Science and Technology |
| Volume | 77 |
| Issue number | 7-8 |
| DOIs | |
| State | Published - 2021 |
| Externally published | Yes |
Funding
The authors thank and appreciate valuable discussions with B. D. Kelly, P. Calderoni, and the participants in the U.S. Blanket Program. This work was prepared for the U.S. Department of Energy, Office of Fusion Energy Sciences, under the DOE Idaho Field Office contract number DE-AC07–05ID14517. The authors thank and appreciate valuable discussions with B. D. Kelly, P. Calderoni, and the participants in the U.S. Blanket Program. This work was prepared for the U.S. Department of Energy, Office of Fusion Energy Sciences, under the DOE Idaho Field Office contract number DE-AC07?05ID14517.
| Funders | Funder number |
|---|---|
| U.S. Department of Energy | DE-AC07?, 05ID14517, DE-AC07–05ID14517 |
| Fusion Energy Sciences |
Keywords
- PbLi
- breeding blanket
- membranes
- permeation
- tritium
