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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Enrico Lucon
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 289-294
Fusion Materials | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8916
Articles are hosted by Taylor and Francis Online.
Within the European Fusion Development Agreement (EFDA) Long Term Programme activities on Material Research, several versions of EUROFER ODS (Oxide-Dispersion Strengthened) have been produced and characterized. The most promising ones to date are the so-called "2nd generation" ODS (HIPped, hot rolled and thermomechanically treated) and the "EU batch" (produced by Plansee in the form of hot rolled plates and extruded bars). These two materials have been mechanically characterized in the unirradiated condition at SCKCEN in collaboration with other European institutes by means of tensile, impact and fracture toughness tests. The same characterization has been performed at SCKCEN on the two materials after low dose irradiation at 300°C in the BR2 test reactor (1.5-1.7 dpa). The results are compared with available data from early versions of EUROFER ODS and conventional (i.e. non-ODS) EUROFER, unirradiated and irradiated under similar conditions. It is confirmed that even the most advanced ODS steels show higher tensile strength than the base material, but also significantly worse fracture toughness properties. On the other hand, the "EU batch" irradiated to 1.52 dpa shows comparatively limited irradiation sensitivity.