ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
Elie Saad, Normand Laurent Laberge, Xiangdong Feng
Nuclear Technology | Volume 86 | Number 1 | July 1989 | Pages 66-69
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT89-A34283
Articles are hosted by Taylor and Francis Online.
Compositional and structural considerations are used to understand viscous behavior of multicomponent borosilicate glasses used in the immobilization of high-level nuclear waste. The presence of alkali and alkaline earth oxides in these systems can be considered as diluents to a highly viscous silica matrix. The extent of dilution is characterized by the presence of singly bonded or nonbridging oxygens. For the analysis, the Arrhenius equation is combined with the number of nonbridging oxygens to develop a predictive temperature-dependent model for the viscosity of these systems based on composition.
