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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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.
N. Ketzlach
Nuclear Technology | Volume 42 | Number 1 | January 1979 | Pages 65-70
Technical Paper | Chemical Processing | doi.org/10.13182/NT79-A32162
Articles are hosted by Taylor and Francis Online.
Subcommittee 8 of the Standards Committee of the American Nuclear Society has conducted the prescribed five-year review and update of ANSI N16.4-1971, which provides guidance for the use of borosilicate glass Raschig rings as a neutron absorber in solutions of highly enriched fissile materials. The proposed revision to the Standard extends its application to low enriched 235U fuels based on the 235U concentration in the vessel and to a limited range of alkaline environments. It incorporates standard American Society for Testing and Materials chemical acceptance tests for the glass, a chemical acceptance test for its acceptability in an alkaline environment, and a test that provides information on volume loss due to chemical reaction in addition to that due to settling.