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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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
Canada clears Darlington to produce Lu-177 and Y-90
The Canadian Nuclear Safety Commission has amended Ontario Power Generation’s power reactor operating license for Darlington nuclear power plant to authorize the production of the medical radioisotopes lutetium-177 and yttrium-90.
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.
