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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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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.
E. Dow Whitney, Dae Joon Kim, Dennis S. Tucker+
Nuclear Technology | Volume 69 | Number 2 | May 1985 | Pages 154-160
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33626
Articles are hosted by Taylor and Francis Online.
The containment of an aggressive high-temperature reactive fluoride atmosphere, such as exists in a pulsed gaseous core nuclear system, requires the use of protective materials that will either not react in this environment or will form stable nonvolatile fluorides, thus passivating the surface against further reaction. Candidate protective materials for gaseous core reactors were identified for further investigation on the basis of their thermodynamic and mechanical properties. Materials included aluminum oxide (Al2O3), yttrium oxide (Y2O3), mixtures of Al2O3 and Y2O3, magnesium oxide (MgO), and pyrophyllite [Al2(Si2O5)2(OH)2]. Pioneering studies at the University of Florida on the use of infrared reflection spectroscopy (IRRS) for nondestructive surface analysis, along with x-ray diffraction pattern (XDP) studies, were applied to the analysis of UF6 material/surface interactions. Candidate materials were subjected to a UF6 atmosphere (973 K, 87 Torr, with 1- to 5-h exposures). The IRRS and XDP analyses of the materials after exposure showed no surface product formation in the case of the first four protective materials. For pyrophyllite, a mechanically and chemically stable protective surface fluoride film was formed.