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November 9–12, 2025
Washington, DC|Washington Hilton
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NNSA awards BWXT $1.5B defense fuels contract
The Department of Energy’s National Nuclear Security Administration has awarded BWX Technologies a contract valued at $1.5 billion to build a Domestic Uranium Enrichment Centrifuge Experiment (DUECE) pilot plant in Tennessee in support of the administration’s efforts to build out a domestic supply of unobligated enriched uranium for defense-related nuclear fuel.
Ehud Greenspan, George H. Miley
Fusion Science and Technology | Volume 2 | Number 4 | October 1982 | Pages 590-608
Technical Paper | Plasma Engineering | doi.org/10.13182/FST82-A20800
Articles are hosted by Taylor and Francis Online.
Partially catalyzed deuterium (PCD) fuel cycles and their sensitivity to ash buildup, radiation losses, Ti/Te. and 3He consumed are investigated. The study is machine independent, using a simple zero-dimensional steady-state model. The PCD fuel cycles include semi-catalyzed-deuterium where only a fraction of the 3He fuses and tritium-catalyzed-deuterium where 3He extracted from the plasma is converted into tritium, which is reinjected. Also considered is tritium-assisted operation where a fraction of the fusion neutrons is used to produce tritium, which is added to the PCD plasma. The PCD and tritium-assisted operation is shown to be attractive for certain nonelectrical applications. They avoid 3He recirculation required for catalyzed-deuterium (Cat-D) operation and enable simplified blanket designs. The ignition temperature, neт, and power density of PCD plasmas are very energy-balance sensitive, but under certain conditions these properties can be comparable or superior to those of Cat-D. Cyclotron radiation losses can significantly impair, whereas tritium assistance can strongly improve, PCD performance.