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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
2022 ANS Winter Meeting and Technology Expo
November 13–17, 2022
Phoenix, AZ|Arizona Grand 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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Sep 2022
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Nuclear Science and Engineering
October 2022
Nuclear Technology
Fusion Science and Technology
Latest News
The DRUM program: Cataloging America’s abandoned uranium mines
Based on a review of U.S. Atomic Energy Commission (AEC) records and available data from numerous agencies, there are an estimated 4,225 mines across the country that provided uranium ore to the U.S. government for defense-related purposes between 1947 and 1970. To aid in the cleanup of these legacy uranium mines and establish a record of their locations and current conditions, the Defense-Related Uranium Mines (DRUM) program was established within the Department of Energy’s Office of Legacy Management (LM).
Technical Session|Sponsored by Advanced Reactors
Friday, April 15, 2022|9:45–11:15AM CDT|Excellence Room
Sponsored by
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A Method for Bubble Detection in Molten Salts using an Acoustic Resonator
Hayden S. Bland (NCSU), Matthew W. Field (NCSU), Christopher Williams (NCSU Department of Nuclear Engineering), Miranda Moultrie (NCSU Department of Nuclear Engineering)
Summary
Study of Bypass Flow in Prismatic Core Using One-Twelfth of the HTGR Core
Harish Aryal (University of Texas of the Permian Basin), Bishal Lamichhane (The University of Texas of Permian Basin)
Uranium Core Design for the Versatile Test Reactor
Andrew Taylor (NCSU), Anna Isom (NCSU), Jordan Page (NCSU), Jamison Harris (NCSU), Saoud Henzab (NCSU), Scott Palmtag (NCSU)
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