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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.
Meeting Spotlight
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
Standards Program
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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Fusion Science and Technology
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.
P. A. Finn, E. H. Van Deventer
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 783-790
Tritium Properties and Interactions with Material | Proceedings of the Third Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Toronto, Ontario, Canada, May 1-6, 1988) | doi.org/10.13182/FST88-A25230
Articles are hosted by Taylor and Francis Online.
The heterogeneous reaction between oxygen/helium gas, tritium and stainless steel was studied at the back surface of a stainless steel tube. The yield of tritiated water was determined as a function of oxygen concentration, tritium concentration, protium concentration, flow rate, and temperature. This report describes the results for two sets of runs done at 550°C with and without 15 ppm protium in the oxygen/helium gas. At oxygen concentrations of 40 ppm, the presence of excess protium in the oxygen/ helium produced a reduced yield of tritiated water. At oxygen concentrations >1000 ppm, the two yields were equivalent, 98%.
