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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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.
H. O. Menlove, R. H. Augustson, Darryl B. Smith
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 366-379
Technical Paper | Analysis | doi.org/10.13182/NT71-A30970
Articles are hosted by Taylor and Francis Online.
A technique has been developed for the nondestructive assay of fissionable materials which makes use of the variations with energy in the fission cross section for a given isotope in order to produce a signature characteristic of that isotope. The technique consists of irradiating the sample with neutrons from an accelerator and measuring the delayed-neutron response from the induced fission reactions in the sample. Different neutron irradiation energies were obtained by surrounding a 14-MeV neutron source with various moderating assemblies. Assay results obtained using this delayed-neutron technique include the following: (a) uranium samples with enrichments ranging from ∼3 to 98%; (b) plutonium-uranium oxides; (c) 233u-232Th salt mixtures; (d) “spent” reactor fuel elements; and (e) scrap containers ranging in size from small vials to one-gallon cans containing plutonium or uranium scrap. In addition, measurements have been made on the influence of various nonfissionable matrix materials on the assay results.