ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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Latest News
Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
William R. Bohl, Dirk Wilhelm
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 366-373
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34720
Articles are hosted by Taylor and Francis Online.
The origins and goals of the advanced fluid dynamics model (AFDM) program are described, and the models, algorithm, and coding used in the resulting AFDM computer program are summarized. Two boiling pool calculations are presented, the first of an experiment with volume-heated water, the second of a sample fuel/steel pool that is compared with a similar SIMMER-II calculation. A subjective assessment of the AFDM developments is given. It is concluded that a future severe accident code development program might be more oriented toward identification of generic or typical accident sequences rather than attempting to address all uncertainties.
