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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.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
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.”
S. Usman, B. S. Mohammad, S. Abdallah
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 310-318
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3878
Articles are hosted by Taylor and Francis Online.
Transient response of a natural convection system is investigated by numerical simulation using FLUENT code. An integrator circuit analogy was recently proposed for natural convection systems. The proposed analogy was further confirmed by these recent simulations. New simulation results also suggest that a natural convection system acts as a "low-pass" filter for transients. Transmission characteristics of a natural convection system were investigated using sinusoidal temperature at the source-side boundary. Transient transmission factor was found to be a function of both fluid properties and the flow characteristics. Transmission factor was also found to be a strong function of fluctuation frequency. These results may prove a significant design tool for Generation IV natural convection systems, particularly for lead-cooled fast reactors or molten salt reactors.