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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
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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Latest News
Sam Altman steps down as Oklo board chair
Advanced nuclear company Oklo Inc. has new leadership for its board of directors as billionaire Sam Altman is stepping down from the position he has held since 2015. The move is meant to open new partnership opportunities with OpenAI, where Altman is CEO, and other artificial intelligence companies.
Jae-Uk Lee, Dong-you Chung, Hyun-goo Kang, Min Ho Chang, Pil-Kap Jung
Fusion Science and Technology | Volume 80 | Number 3 | May 2024 | Pages 582-589
Research Article | doi.org/10.1080/15361055.2023.2202302
Articles are hosted by Taylor and Francis Online.
In this study, the amount of 3He release from a tritium-loaded depleted uranium bed considering long-term operation in the fusion fuel cycle is assessed using empirical models. Several works are surveyed to investigate the trend of 3He released from uranium tritide. The model for 3He release is developed consisting of two parts, i.e., the natural release model and the heating release model, based on experimental studies. The natural release model is validated by applying it to experimental data. The model is applied to cyclic and long-term operation scenarios to assess the amount of 3He in the headspace of the metal tritide bed. The results show that the 3He release after long-term maintenance can be significant and must be separated from tritium before supply to the fuel cycle. During plasma operation and short maintenance, it is shown that the 3He release is less significant, but further requirement consideration is needed for the 3He separation process.