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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Apr 2025
Jan 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
Technical Session|Sponsored by RPSD
Tuesday, June 15, 2021|4:30–6:15PM EDT
Session Chair:
Yuefeng Qiu
Session Organizer:
Alternate Chair:
Chelsea A. D'Angelo
Staff Producer:
Julie Bry (ANS)
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MCNP Unstructured Mesh Code Verification for OKTAVIAN Benchmark
Harrison Leiendecker (LANL), Alex Warhover (LANL), Jerawan Armstrong (LANL), Jim Ferguson (LANL)
Paper
Recent Work on MCNP Unstructured Mesh Element Quality Assessment and Reporting
Joel A. Kulesza (LANL)
Neutron Dose Rate Calculation with the MCNP6 Hybrid Geometry Model of the Second Target Station
Lukas Zavorka (ORNL), Igor Remec (ORNL)
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