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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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.