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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
Latest News
INL makes first fuel for Molten Chloride Reactor Experiment
Idaho National Laboratory has announced the creation of the first batch of enriched uranium chloride fuel salt for the Molten Chloride Reactor Experiment (MCRE). INL said that its fuel production team delivered the first fuel salt batch at the end of September, and it intends to produce four additional batches by March 2026. MCRE will require a total of 72–75 batches of fuel salt for the reactor to go critical.
J. L. Maienschein, F. E. McMurphy, F. S. Uribe
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 775-782
Tritium Properties and Interactions with Material | Proceedings of the Third Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Toronto, Ontario, Canada, May 1-6, 1988) | doi.org/10.13182/FST88-A25229
Articles are hosted by Taylor and Francis Online.
Cesium-exchanged Type 4A zeolites can encapsulate high-pressure tritium by physical entrapment in interior pores. We present data on storage capacity related to physical pore volume in the zeolite, and show that storage stability is reasonably good for short periods. Our data also shows that the zeolite releases helium while retaining tritium. Results are analyzed in terms of a diffusion model in the literature. The zeolite showed no structural change after a radiation dose of 108 Gy; it is unclear if radiation affects storage stability.
