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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
L. R. Greenwood, R. R. Heinrich, M. J. Saltmarsh, C. B. Fulmer
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 175-190
Technical Paper | doi.org/10.13182/NSE79-A19462
Articles are hosted by Taylor and Francis Online.
Neutron activation measurements are reported for 44 reactions from 14 materials irradiated in a well-characterized neutron field produced by 40-MeV deuterons impinging on 9Be at the Oak Ridge Isochronous Cyclotron. Foil packets were located at 0 and 15 deg to the beam at 7.62 cm from the source, and additional foil materials were located directly on the deuteron beam stop 6.25 mm from the source. Integral tests were made for 30 reactions using previously measured time-of-flight (TOF) spectra and neutron cross sections, primarily from ENDF/B-IV, extrapolated to 44 MeV. The integral results are excellent, with an overall standard deviation of ±11% for 25 recommended reactions (±14% for 30 reactions), and neutron spectra unfolded with the SAND II code show excellent agreement with TOF measurements.