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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.
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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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Molten salt research is focus of ANS local section presentation
The American Nuclear Society’s Chicago–Great Lakes Local Section hosted a presentation on February 27 on developments at the molten salt research reactor at Abilene Christian University’s Nuclear Energy Experimental Testing (NEXT) Lab.
A recording of the presentation is available on the ANS website.
Donald G. Schweitzer
Nuclear Science and Engineering | Volume 13 | Number 3 | July 1962 | Pages 275-282
Technical Paper | doi.org/10.13182/NSE62-A26164
Articles are hosted by Taylor and Francis Online.
A summary is given of the work done on the thermal behavior of air-cooled graphite channels. The differences in results between this work and work done by Robinson and Taylor (5) appear to arise from the different models used. The results reported here and re-evaluation of the Robinson and Taylor work indicate that their model is not confirmed by their experiments and does not predict the limit in permissible temperatures imposed by graphite oxidation in air-cooled graphite moderated reactors.
