Dear colleagues, Please consider participating in a technical session on spent nuclear fuel disposal at the 2023 Clay Minerals Society Annual Meeting. The meeting will be held **May 20-25 in Austin, Texas**. Here is a link to the meeting website. Abstract submission deadline is **February 6, 2023**. [https://cvent.utexas.edu/event/b8822615-d0e8-4730-89e4-2ef519cbeb5b/summary](https://gcc02.safelinks.protection.outlook.com/?url=https%3A%2F%2F149.156.2.140%2Ffmlurlsvc%2F%3FfewReq%3D%3AB%3AJVw4Mzc6OCR0PzAsMiRrZj8yMzgyMyRxa2VsY3Z3cGc%2FZztgNDBgNmM0Z2Q0YDRjMDEyYTthNTAyNWBgYzNhY2cwMzEzYzc7ZyR2PzM0NDoxNTc0MjAkc2tmPzBDRk5nM0tMMjMwNjI6LzBDRk5nM0tSMjMwNjI6JHBhcnY%2FYyxmZ3BpbXVxaWtCa2xlcmNsLGlwY2ltdSxybiRhPzEyJGpmbj8y%26url%3Dhttps%253a%252f%252fcvent.utexas.edu%252fevent%252fb8822615-d0e8-4730-89e4-2ef519cbeb5b%252fsummary&data=05%7C01%7Cjagreat%40sandia.gov%7Cc02b31ae1a8b40bd523308dad49fec62%7C7ccb5a20a303498cb0c129007381b574%7C1%7C0%7C638056080585543519%7CUnknown%7CTWFpbGZsb3d8eyJWIjoiMC4wLjAwMDAiLCJQIjoiV2luMzIiLCJBTiI6Ik1haWwiLCJXVCI6Mn0%3D%7C3000%7C%7C%7C&sdata=klcSClDyeCUS1k9KRU3N3TsbylBpqLaH5vDnwJlGR7s%3D&reserved=0)   **Current trends in research and development of bentonites for the isolation of spent nuclear fuel** Jeffery Greathouse, Nuclear Waste Disposal Research and Analysis Department, Sandia National Laboratories Tuan Ho, Geochemistry Department, Sandia National Laboratories Marcelo Sánchez, Department of Civil and Environmental Engineering, Texas A&M University Smectite clay minerals play an important role in underground nuclear waste repository concepts due to their ability to hinder the transport of aqueous cations through ion exchange and adsorption. In particular, bentonites have been considered for engineered barrier systems and as the primary constituent of surrounding host rock, to prevent or hinder the transport of radionuclides in the subsurface. This session seeks to survey current trends in the research and development activities related to bentonites as barrier materials for isolation of spent nuclear fuel. Examples include, but are not limited to: temperature/humidity/chemical effects, thermomechanical properties, ion, water, and gas (e.g., H2) adsorption and transport. Contributions are welcome from fundamental studies to the industrial development of repository concepts. Methods can involve experimental investigation to molecular, constitutive, and numerical modeling. The aim of this session is to gather experts from multiple disciplines to identify critical research and development needs.  **Invited speakers:** Ian Bourg, Princeton University Florie Caporuscio, Los Alamos National Laboratory Arek Derkowski, Polish Academy of Sciences Andrey Kalinichev, IMT Atlantique John McCartney, University of California, San Diego Michael Whittaker, Lawrence Berkeley National Laboratory LianGe Zheng, Lawrence Berkeley National Laboratory Kind regards, Jeffery Greathouse Sandia National Laboratories