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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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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.”
Motoo Fumizawa, Tomoaki Kunugi, Makoto Hishida, Mikio Akamatsu, Sadao Fujii, Minoru Igarashi
Nuclear Technology | Volume 110 | Number 2 | May 1995 | Pages 263-272
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35124
Articles are hosted by Taylor and Francis Online.
A three-dimensional thermal-hydraulic code using boundary-fitted coordinates systems has been developed to predict incompressible flows with complex geometries and large variations of physical properties. This code has been applied to a buoyancy-driven exchange flow in an enclosed space consisting of an upper and a lower hemisphere connected with a circular vertical pipe. The computational results have been compared with experiments. It was found that the computed heat transfer rate was smaller than that obtained from the experimental correlation in a single hemisphere at large Rayleigh number. This may be attributed to the effect on the flow behavior of a large variation of gas properties. Unsteady and asymmetric flow patterns such as observed in the experiments were numerically obtained in the vertical pipe.