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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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
American Fuel Resources requests license for N.M. uranium deconversion plant
American Fuel Resources, a provider a nuclear fuel cycle solutions headquartered in Spokane, Wash., has submitted an application to the Nuclear Regulatory Commission requesting transfer of a materials license from Idaho-based radioisotope manufacturer International Isotopes for a depleted uranium hexafluoride (DUF6) deconversion plant in Lea County, N.M.
Sean M. McDeavitt, David Wootan, Mark Kimber, Karen Vierow Kirkland, Luis H. Ortega, Delia Perez-Nunez, Pavel Tsvetkov, Jason Hearne, Abdullah Weiss, Saleem Drera, Nicolas E. Woolstenhulme
Nuclear Science and Engineering | Volume 197 | Number 11 | November 2023 | Pages 2840-2852
Regular Research Article | doi.org/10.1080/00295639.2023.2166765
Articles are hosted by Taylor and Francis Online.
Two of the experiment vehicles being developed for the Versatile Test Reactor (VTR) are presented here. The first is a rabbit system that will enable rapid insertion of small test capsules into the high fast flux of the VTR core for relatively short durations. The rabbit concept development includes the construction/demonstration of a near-full-scale system in a deep-water pool to demonstrate functionality, development of a concept of operations and initial procedures, and validation of thermal-hydraulic modeling. In addition, modeling efforts are underway to simulate the thermal and neutronic environment of a rabbit capsule. The second type of experiment vehicle presented here is a driver fuel test assembly for inserting fuel and materials tests into the core by replacing a driver fuel assembly. A novel design for dismountable test assemblies is proposed for the VTR.