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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
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.