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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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. M. Garrison, G. L. Kulcinski
Fusion Science and Technology | Volume 64 | Number 2 | August 2013 | Pages 216-220
Materials Development | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 1), Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST13-A18079
Articles are hosted by Taylor and Francis Online.
Single crystal tungsten samples with orientation (110) were irradiated in the Materials Irradiation Experiment with normal incidence 30 keV He+ at 900 aC. Samples were mechanically polished and then electropolished with a KOH solution before irradiation to 3×1017 to 6×1018 He+/cm2. With increasing fluence sample surface pore size increased from ~20 nm to more than 100 nm. Mass loss also increased with fluence to a maximum of 15 g/m2 lost for the highest fluence sample.