ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
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!
Latest Magazine Issues
Jan 2025
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Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
Survey says . . . Emotional intelligence important in nuclear industry
The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
Gerard L. Hofman, George L. Copeland, John E. Sanecki
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 338-344
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Nuclear Fuel | doi.org/10.13182/NT86-A33772
Articles are hosted by Taylor and Francis Online.
The recent emphasis on profileration-resistant fuels for research and test reactors has resulted in additional investigations of well-established fuels, such as U3O8-Al dispersions, to determine their behavior at the higher fuel densities required for the lower uranium enrichment. Microstructural investigation of these irradiated fuels with modern techniques has provided insight into the fission gas behavior and its relationship to the U3O8-Al interaction during irradiation. These observations explain the observed limitations on fuel loading and safe levels of fission density achievable with these fuels.
