ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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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Nuclear Science and Engineering
May 2025
Nuclear Technology
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.
D.M. Strachan, R. P. Turcotte, B. O. Barnes
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 306-309
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32859
Articles are hosted by Taylor and Francis Online.
A Materials Characterization Center (MCC) has been established by the U.S. Department of Energy at the Pacific Northwest Laboratory (PNL). Five proposed standard leach tests and typical results using the MCC-1 static test are presented. For the boro-silicate glass studied (PNL 76-78), fivefold replicate experiments show that errors in elemental leach values are usually less than ±10%. Regular time-dependent leach curves are obtained, and no significant difference is observed between pure water and simulated silicate/bicarbonate groundwater results. Leaching in salt brine is quite different, especially as shown by elemental depth profiles in the solid; these profiles show significant magnesium penetration into the gel layer from the brine solution.