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
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.
Prodyot Roy, C. N. Spalaris
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 259-269
Technical Paper | Materials | doi.org/10.13182/NT55-259
Articles are hosted by Taylor and Francis Online.
A development program was undertaken to support the materials selection for steam generator piping and intermediate heat exchangers that are to be used in liquid-metal fast breeder reactors. Four major topics have been reviewed, and the results obtained as well as the direction of future tests have been described. These topics are carbon transport in sodium, the effect of carbon loss/gain on materials in the reactor intermediate heat transport system (IHTS), corrosion fatigue, and aqueous corrosion. Thus far, the results on hand support the initial assumptions made in specifying the use of Cr—1 Mo as the construction material for the evaporator and superheater and Type 316 piping of the IHTS. The future direction of the experimental programs is to verify further the materials choice and also to obtain information that will be essential during the plant installation and operation and the reliability of the components.