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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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.
G. R. Odette, T. O. Ziebold
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 72-81
Technical Paper | doi.org/10.13182/NSE72-A22528
Articles are hosted by Taylor and Francis Online.
An experiment was performed to measure the energy-dependent damage function for the neutron irradiation induced increase in the lower yield strength of iron. Small tensile test specimens were exposed at low temperatures (<100°C) to 1017 - 1018 n/cm2 (E > 1 MeV) in seven reactor spectra while a high degree of consistency among all other variables known to be significant was maintained. The neutron flux spectra in all locations were measured using the multiple foil activation technique and the SAND-II code for the data analysis. The mechanical property and flux spectral data were then analyzed using SAND-II to unfold the damage functions. Estimates of errors induced in the solution by the iterative unfolding procedure were made considering possible contributions from both the lack of mathematical solution uniqueness and data error propagation.