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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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Latest News
Leading the charge: INL’s role in advancing HALEU production
Idaho National Laboratory is playing a key role in helping the U.S. Department of Energy meet near-term needs by recovering HALEU from federal inventories, providing critical support to help lay the foundation for a future commercial HALEU supply chain. INL also supports coordination of broader DOE efforts, from material recovery at the Savannah River Site in South Carolina to commercial enrichment initiatives.
R.A. Causey, K.L. Wilson, W.R Wampler, B.L. Doyle
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1585-1588
Material and Tritium | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29567
Articles are hosted by Taylor and Francis Online.
For the next generation of fusion reactors, tritium inventory will be one of the greatest safety concerns. Both CIT and ITER call for the use of graphite or carbon composites as the first wall and divertor material. If this graphite should contain a large number of traps for the storage of tritium, the resulting inventory could restrict the operation of the reactor. This report presents the results of an experimental study on the effects of neutron irradiation on the trapping of tritium in graphite. Enhancements in the trapping levels by two orders of magnitude up to as high as 0.2 atomic percent were seen for graphite samples irradiated to approximately 10 dpa at different temperatures. The results are compared to those obtained for ion damaged samples. The implications of the results for the operation of CIT and ITER are examined.
