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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
Leading the charge: INL’s role in advancing HALEU production
Idaho National Laboratory is playing a key role in helping the U.S. Department of Energy meet near-term needs by recovering HALEU from federal inventories, providing critical support to help lay the foundation for a future commercial HALEU supply chain. INL also supports coordination of broader DOE efforts, from material recovery at the Savannah River Site in South Carolina to commercial enrichment initiatives.
Jonathan Scherr, Pavel Tsvetkov
Nuclear Technology | Volume 209 | Number 11 | November 2023 | Pages 1733-1746
Regular Research Article | doi.org/10.1080/00295450.2023.2209229
Articles are hosted by Taylor and Francis Online.
Abilene Christian University (ACU) is developing a 1-MW(thermal) molten salt research reactor that will be built on the ACU campus. A conceptual reactor core model was developed to facilitate the safety analysis required for a construction permit. A series of scoping studies were performed seeking to define the reactor core design parameters subject to a variety of design requirements. A Pareto curve identifying the tradeoff between uranium and LiF-BeF2 was determined. Within this curve, at least 250 kg of uranium and 700 kg of LiF-BeF2 are needed, albeit for different reactor configurations and fuel salt compositions. The cylindrical reactor vessel associated with the best-performing fuel salt composition is ~130 cm in diameter, ~170 cm tall, and contains ~2.5 tons of graphite. The conversion ratio of the reactor is low and will require regular refueling. The shift in neutron spectrum observed with the changing fuel salt composition does not significantly impact reactivity loss with respect to burnup.