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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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.”
Lainsu Kao, Mujid S. Kazimi
Nuclear Technology | Volume 78 | Number 2 | August 1987 | Pages 170-184
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A33995
Articles are hosted by Taylor and Francis Online.
Analyses of the concrete attack and ex-vessel aerosol release using various assumptions for the molten corium/concrete interaction have been performed. The study involved variations in several parameters, such as initial debris temperature, amount of unoxidized zirconium, amount of melt, concrete ablation temperature, and concrete type. At high initial corium temperatures the periodic contact (nucleate-boiling-like) model leads to more rapid concrete attack, higher decomposition gas release, and higher fission product release than the gas film model. At low initial corium temperatures, when a corium crust is initially formed, the various heat transfer models do not lead to significant differences in the fission product releases. Besides the initial debris temperature, the most significant parameter in prediction of the fission product release is the amount of unoxidized zirconium. Among the various fission products, the nonvolatiles, such as lanthanum, are more sensitive to changes in the parameters.