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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
E. Alves, L. C. Alves, N. Franco, M. R. Da Silva, A. Paúl
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 233-237
Technical Paper | Beryllium Technology | doi.org/10.13182/NT07-A3870
Articles are hosted by Taylor and Francis Online.
The improved mechanical and chemical properties of intermetallic beryllium compounds make them good candidates to replace metallic beryllium in future fusion power plants. Titanium beryllide is a compound with low chemical reactivity, which makes it very attractive for fusion applications. In this work we study the structural stability of titanium beryllides and the oxidation behavior under air annealing. Both high-resolution X-ray diffraction and microbeam techniques were used to follow the evolution of the composition and crystalline phases as well as the microstructure. Beryllium-titanium intermetallic compounds were produced using two alloys with a nominal composition of Be-5 at.% Ti and Be-7 at.% Ti. The as-cast samples show the presence of Be10Ti for the Be-7 at.% Ti alloy, while the Be12Ti phase was mostly found in the Be-5 at.% Ti compound. While the Be-5 at.% Ti alloy reveals large intragrain regions with high concentration of impurities (O, Fe) and Ti depletion, the Be-7 at.% Ti shows a more homogeneous structure. During thermal treatments up to 800°C in dry-air atmosphere, the oxidation occurs preferentially at the beryllium-rich regions. No evidence was found for phase separation during the annealing in vacuum.
