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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Survey says . . . Emotional intelligence important in nuclear industry
The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
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.