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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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NEI chief executive highlights “unlimited potential” for nuclear in state of the industry address
Korsnick
In the Nuclear Energy Institute’s annual State of the Nuclear Energy Industry report, NEI president and CEO and Maria Korsnick expressed optimism about the nuclear industry and she issued a call to action.
Her address was part of NEI’s Nuclear Energy Policy forum. The forum, being held in Washington, D.C., on May 20 and May 21, brings together industry leaders, policy stakeholders, and clean energy experts to discuss nuclear advocacy. Korsnick’s remarks focused on the private capital flowing into the industry, progress on regulatory reform and new nuclear technology, and how the U.S. is trying to take the lead on the global nuclear stage.
“We are here at an unprecedented time in our industry history,” Korsnick said. “I’m proud to say that the nuclear industry has a future of unlimited potential.”
V. K. Chandola, S. K. Loyalka
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 434-446
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32902
Articles are hosted by Taylor and Francis Online.
Computation of nuclear reactor fuel behavior under normal and off-normal conditions is influenced by gap conductance models. In this paper the gap conductance results obtained by the use of the GAPHTR model and a new model that has a more sound theoretical basis in the jump regime are compared for small gaps with the modified pulse design experimental data. The new model is found to provide a better and more satisfactory prediction of the experimental data.
