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
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
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.